UNITED STATES

ATOMIC ENERGY COMMISSION DIRECTORATE OF REGULATORY OPERATIONS

REGION III

799 ROOSEVELT ROAD TELEPHONE

GLEN ELLYN, ILLINOIS 60137 (312) 858-2660

A. RO Inspection Report No. 50-305/74-15

Transmittal Date December 11, 1974

Distribution: Distribution: RO Chief, FS&EB RO Chief, FS&EB RO:HQ (5) RO:HQ (4) DR Central Files L:D/D for Fuels & Materials egul atory Standards (3) DR Central Files

Licensing (13) RO Files RO Files

B. RO Inquiry Report No.

Transmittal Date :

Distribution: Distribution: RO Chief, FS&EB RO Chief, FS&EB RO:HQ (5) RO:HQ DR Central Files DR Central Files Regulatory Standards (3) RO Files Licensing (13) RO Files

C. Incident Notification From:

(Licensee & Docket No. (or License No.)

Transmittal Date .

Distribution: Distribution: RO Chief, FS&EB RO Chief, FS&EB RO:HQ (4) RO:HQ (4) Licensing (4) L:D/D for Fuels & Materials DR Central Files DR Central Files RO Files RO Files

*Ilp c 4c~ UNITED STATES

ATOMIC ENERtiY COMMISSION *:D3RECTORATE- OF REGULATORY OPERATIONS

REGION III TE0 799 ROOSEVELT ROAD TELEPHONE

GLEN ELLYN, IL..NOIS 60137 312i 858-2660

DEC. 11 1

-*i . Docket o.0305 viscenmatrh Pabic sice cop ain okeN. os

'Pveri iejeaton and Engibns

P. 0. Bo 1200 Greenli Bay, W Vi~In' 54305 on a emtne

-Il~cd~ 'W'D.4'.'otldv

n - y- fC on. This refer to he inspection conducted by ir. D. Boyd of thisf of fice on September 25s otobr 2 8t 11, 2-7 22 and 24, ovmber 4, 13 a 1s, 1974, of at isat ofia:n*e udc-a Powr Station tsee by Ase ope asing Licse No. DPR-4 and to thediscu n oour idi w Mr.Loa au othrs of your stfat te conclusion of the inpectin. -copy of aour reIIIt tis tosetion seloed and

arasezmi~dtoin th ouetin Wiinu~ -o id011f4ooth

si. iareon th tsp.etion 'coastedo ad arletveannton of procedures and represent

-astieeod &I' interie s with plant personnel, and observations by h inspeetor............. *

0 During this inapectin, tw fouad that er tain oyoue 'a toe t appear, t be in violation of AEC requireets. The iem and referec to the pertinn rereents aire litedia under aorcuedt Actio in t summary of .ifideseti of the enclse specion pr Prir t the concluion of te inspecton, te inspeor determtned tha te

S- action had been taken with e t to this violation aind that is n hiave ben\ taken to assure that a s inar, future violation vill'i avoided. consequently, no rely to ha letter is reqirned, and hv no futher-questions regardina this matter at this ta

i cordance ih cin 2.90 of the 's "Rle of Practic" -Pa 2, Tie 1, Code of ederal Regulation, a copy ofthis lete and the

enclosed inspection report will be placed in the40aC Public Documni soons. Ifthis rept contais any itiokmaston that you or yodr conktactors beitev to be prpretary, it is necessary that you make a . t witen applatio to th is office, wihiteAla nty dye of youe resept

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U. S. ATOMIC ENERGY COMMISSION

DIRECTORATE OF REGULATORY OPERATIONS

REGION III

NOVEMBER R.I.P. REPORT

Report of Operations Inspection

RO Inspection Report No. 050-305/74-15

Licensee: Wisconsin Public Service Corporation

P. 0. Box 1200 Green Bay, Wisconsin 54305

Kewaunee Nuclear Power Plant License No. DPR-43

Kewaunee, Wisconsin Category: C

Type of Licensee: PWR 560 Mwe (W)

Type of Inspection: Resident Inspection Program

Dates of Inspection: September 25, October 2, 8, 11, 17, 22, 24;

November 4, 13, and 15, 1974

Dates of Previous Inspection: August 1, 6, 14, 19, 20, 27, 29 and September

4, 1974 (R.I.P Boyd)

Principal Inspector: By '(DAte)

Accompanying Inspector: None

Other Accompanying Personnel: T. Harpster

(November 13 & 15

1974)

Reviewed By: Ea/ Seni r Reactor (Date) Reactor Operations Branch

SUMMARY OF FINDINGS

Enforcement Action:

The following violation identified by the licensee, is considered to be

of Category III Severity:

1. Environmental Technical Specifications (Appendix B), Section 4.1.1.b.1,

Fish Impingement, states, "The number, size and weight of all

.species collected in the circulating water trash basket shall be

identified by plant personnel on a daily basis. If the numbers

of the impinged species."

Contrary to the above, the licensee reported that the fish impingement

data had not been recorded on a daily basis. (Paragraph 9)

Licensee Action on Previously Identified Enforcement Matters: None.

Unusual Occurrences:

A. September 20, 1974, Radiation monitoring units R-11, R-12, switch

in an improper position. (Paragraph 4.a)

B. September 26, 1974, Temporary loss of power to instrument bus four.

(Paragraph 4.b)

C. October 15, 1974, Failure of RTD loop isolation valve. (Paragraph 4.c)

D. October 15, 1974, Malfunction of safety injection isolation valve.

(Paragraph 4.d)

E. October 25, 1974, Failure of auxiliary feedwater pump to start.

(Paragraph 4.c)

Other Significant Findings

A. Current Findings

The outage which began on September 19, 1974, to change over to a

volatile steam generator chemistry control and to perform baseline

eddy current testing of steam generator tubes, was completed on

October 19, 1974.

The unit is currently operating at reduced power due to mechanical

problems in "B" main feedwater (FW) pump.

B. Unresolved Items: None.

C. Status of Previously Reported Unresolved Items: None.

b - 2-

Management Interview

The management interview was conducted on November 15, 1974, with Messrs.

Luoma and Lange. Mr. T. Harpster of RO:III accompanied D. Boyd, resident inspector, during the management interview.

Items discussed included the following:

A. Unusual Occurrences

1. R-ll, R-]2 switch position. (Paragraph 4.a)

2. Temporary loss of power to bus four. (Paragraph 4.b)

3. RTD loop isolation valve failure. (Paragraph 4.c)

4. Isolation valve failure. (Paragraph 4.d)

5. Failure of auxiliary FW pump to start. (Paragraph 4.e)

B. Violations: Fish impingement quantification records. (Paragraph 9)

C. Licensee adherence to administrative control procedures. (Paragraph C)

D. Plant operations review committee meeting minutes. (Paragraph 6)

REPORT DETAILS

1. Persons Contacted

Persons contacted during these inspection include:

Wisconsin Public Service Corporation (WPS)

C. Luoma, Plant Superintendent

R. Lange, Assistant Plant Superintendent

C. Steinhardt, Reactor Supervisor

M. Stern, Reactor Test Engineer

W. Truttman, Operations Supervisor

M. Singh, Shift Supervisor

D. Ristau, Shift Supervisor

W. Wagner, Control Operator

J. Richmond, Technical Supervisor

A. Ninmer, Assistant Maintenance Supervisor

D. McSwain, Instrument and Control Supervisor

T. Moore, Administrative Assistant

2. General

Reports issued under the recently established resident inspector

program (RIP) address areas of inspection completed in the

implementation of the program, and will not report in detail in

each area unless the findings warrent further discussion.

3. Inspection Activities

a. Review of incident report file to October 19, 1974.

b. Review of abnormal occurrence file to October 19, 1974.

c. Observed several shift turnovers. (Both during reactor operation

and reactor shutdown)

d. Observed operator performance of procedures immediately following

reactor scram, and during return to power.

e. Reviewed and observed plant adherence to work request procedures.

(paragraph 5)

f. Observed performance of maintenance activities (RTD manifold

valve repairs; main FW pump seal repair; FW isolation valve

repairs)

g. Reviewed adherence to temporary change to procedure.

b. Accompanied equipment operator on his round for full shift.

i. Reviewed recent abnormal occurrences. (Paragraphs 4.a thru e)

j. Observed and reviewed the plant operations during startup, scram recovery, steady state operation; and during cold shutdown

periods.

k. Performed detailed review of representative plant procedures

in following areas: Administrative; maintenance, operations, abnormal conditions, instrument and control, surveillance, security, and retraining.

1. Reviewed shift logs and records (daily).

m. Reviewed plant operations review committee minutes (to October

19, 1974) (Paragraph 6)

n. Reviewed Nuclear Safety Review and Audit Committee meeting

minutes (to October 19, 1974)

0. Reviewed semi-annual operating report January 1, 1974 to

June 30, 1974.

p. Reviewed and observed use of jumper control logs. (Paragraph 7)

q. Reviewed design change files.

r. Verified normal, auxiliary, and emergency electrical lineup during power operation.

4. Abnormal/Unusual Occurrence Review

The following information was derived from observations, review of

reports, records, and discussion with members of the licensee's

staff.

a. September 20, 1974,

During a reactor outage containment purging was terminated to

draw a sample for analysis. Following the sampling, the

selector switch for radiation monitoring units R-11 and R-12

was placed in the wrong position such that when purging was

continued R-11 and R-12 were monitoring a recirculating purge

flow rather than the actual atmosphere being purged. Radiation

monitor, R-21, down stream of R-11 and R-12 was operating

properly and did provide for monitoring of all releases during

the period of time when R-11 and R-12 were essentially out of

service, (5 hours). Upon discovery that monitors R-11 and R-12

were not monitoring the containment atmosphere being vented,

the filters were removed from monitor R-21, and then taken to

the Laboratory for analysis. Regulatory review of these

analysis results indicate that the Technical Specification release limits were not exceeded.

1/ Abnormal Occurrence Report dtd 10/1/74.

-5-

The cause for this occurrence was found to be "operator error".

The operator was following a procedure but inadvertantly

placed the 3-position selector switch in the wrong position.

2/ b. September 26, 1974.- Temporary loss of Power to Instrument

Bus Four

During a reactor outage, a relay test group requested permission

to perform a specific breaker test. The performance of this

test required that the bus supply be transferred from it's

normal supply to an alternate supply. This transfer failed, leaving instrument bus four de-energized for approximately

twenty minutes. The cause of the transfer failure was found

to be that the battery backup supply breaker was open. The

reason for the breaker being open is not known, i.e., no

authorizations had been issued to permit the opening of this

breaker, and no work requiring this breaker to be open had

been performed. The corrective action taken was to place the

battery room under locked access control by the shift supervisor.

The need for strenghtening adherence to administrative controls

was discussed with the licensee management.

3/ c. October 15, 1974- (Unusual Event) Failure of RTD Loop Isolation

Valve

During preparations for reactor startup a loss of flow condition

was found to exist in the loop A hot leg portion of the RTD

bypass loop.

Investigations which included x-raying of several valves in

this loop indicated that the stem was seperated from the disc

in one valve and that the direction of flow through this

particular isolation valve caused the now free disc to act

as a check valve. Further investigations revealed that only

two valves were installed such that the direction of high

pressure would cause a "Free Disc" to act as a check valve.

Both of these are manual normally open (locked open) isolation

valves in the A and B hot leg RTD by pass loops. Flows in

these loops are recorded and low flow is annunciated in the

control room.

The cause of failure is believed to be that in closing these

valves an attempt is made to close them too tightly. The

valves are designed for approximately 2500 psig pressure and

are usually very difficult to turn. An impact handle is

designed into the valve by the manufacturer to aid in opening

or closing the valve. The failure apparently occurs from

continued impacting after the valve is already either fully

closed or fully open. The valve is a Rockwell Edwards F.

Stainless Steel Univalve, General Assembly Number 3624-F-316J.

2/ Abnormal Occurrence Report dtd 9/27/74.

3/ Unusual Event Report dtd

* -6-

Corrective actions taken were:

1. The faulty valve was replaced with identical valve.

2. An operating instruction was issued identifying the numbers of turns required to open or close these valves.

3. A computer search was run to identify all such valves in the plant. Four were found to be in safety related systems. These were verified to be installed such that, even with a "Free Disc", flow would not be restricted.

d. October 15, 1974- Malufuction of a Safety Injection Isolation Valve

During preparations for reactor startup a limitorque valve in the cold leg injection line was found to be inoperable. This

normally open valve was closed to permit adjustment of an accumulator level. On attempting to reopen the valve it returned to an intermediate position and stopped.

Examination revealed that the valve was in a misalignment bind due to several missing bolts in the upper housing cover. The housing was also found to be cracked. It is believed that the bolts have been missing since construction.

The upper housing cover was replaced, aligned and the valve was functionally tested to verify proper operation.

According to the licensee's records this was the first such failure of this limitorque type SMB-00 operator.

5/ e. October 25, 1974- Failure of an Auxiliary Feedwater Pump to start

During a power reduction to permit repairs of "B" main feedwater pump isolation valve, a HI-HI steam generator water level was experienced. Auxiliary feedwater pump lB started as it should have, but the LA auxiliary feed pump did not start.

Investigations by the licensee revealed that the A relay in the lA Auxiliary feed pump circuit had failed to drop out. The relay, an A. 0. Smith type PM 5V6 relay, is normally closed and drops out upon the loss of normal feedwater flow. It's actuation (dropping out) initiates the start of the appropriate auxiliary feedwater pump. Examination of the relay disclosed that a mechanical interference existed between the stationary coil and the moveable armature, ie., one edge of the armature was in contact with the coil thus adding a friction resistance to the gravity drop of the armature.

4/ Abnormal Occurrence Report dtd 10/23/74. 5/ Abnormal Occurrence Report to be issued by 11/4/74.

-7-

This is the first-such failure of this type relay at this

station. The licensee prepared a listing of all of these type

relays and conducted an examination of each to determine if

proper clearence existed none were found, other than the

failed unit, to have improper clearence.

5. Adherence to Administrative Control Procedures

The inspector made a general plant review for adherence to plant

administrative control procedure No. 5.4, "Clerk Request", clerk

request authorization and control was found to be employeed in all

cases examined where safety related work was being performed.

However, records examined indicate that a relaxation of control

exists for non-safety related work.

In discussing this matter with plant management the inspector was

assured that it is their intent that all major plant maintenance

activites be authorized and controlled in accordance with procedure

5.4, and the inspector was further assured that a dual set of

standards, one for safety related work and one for non-safety

related work is not intended.

6. Plant Operating Review Committee (PORC) Minutes

The inspector reviewed the PORC minutes for the.year. to date and

checked the committee functions against the requirements of the

technical specifications and against the plant administrative

control procedures. All areas were found to be acceptable, however,

one area of weakness was discussed with management. This area was

the backlog of meeting minutes that had not been typed and distributed.

Management stated that they were aware of the problem and had

assigned additional personnel to aid in resolving this problem. A

reinspection, ten days after the initial contact, verified that the

backlog had been cleared.

A review of the offsite safety committee minutes plus discussions

with members of the PORC established that information requiring the

review of the offsite safety committee was communicated to that

committee in a timely fashion (verbally, by individuals who are

members of PORC and the offsite safety committee, or by telecopy)

such that the delay in the distribution of PORC minutes did not

appear to adversely affect the functioning of the safety committee.

7. Jumper Logs

A review of the plant adminstrative control over the use of temporary

jumpers or lifted leads indicates that administrative control

procedure 5.9, jumper control log had now been fully implemented.

The initial inspection, conducted early in October, disclosed that

the maintenance and instrument groups had fully implemented the

procedure but that the operations group was utilizing a temporary

procedure change form for jumper and lifted lead control. A recheck

of this area at months end reveals that operations now has a "Jumper

Log" and numbered certified leads, in accordance with the procedure.

-8

The inspector checked behind all control room panels for the presence

of jumpers and/or lifted leads. No unauthorized jumpers or lifted

leads were found.

8. Staffing

The inspector was informed that one of the stations licensed Senior

Reactor Operators (SRO) has left the company. The company has nine

licensed SRO's remaining, and two other candidates are expected to

receive SRO licenses by mid December, 1974.

A review of the present shift staffing verifies that the plant is

being manned in accordance with the requirements of the Technical

Specifications.

9. Fish Impingement Records

An internal review by the licensee of adherence to the environmental

technical specifications revealed that the procedure being used to

quantify and report the fish collected on the circulating water

screens was not in accordance with the environmental technical

specifications. The licensee had been checking the collection

basket each shift by operations personnel and five times per week

by health physics personnel. The collection basket would be emptied

and the fish quantified whenever the basket was full rather than on

a daily basis as stated in the technical specification.

A review of the collection data by the licensee indicates that the

numbers of fish impinged on the screens is unusually small except

during the cycle fish run periods. The operations staff requested

a change to the technical specification proposing that a records of

the number, size, weight, and species by made, as a minimum, twice

per week. This proposal was accepted by Licensing on November 12,

1974, providing that a collection basket inspection is made every

shift and the quantifying and reporting, above the minimum, is

adjusted accordingly.

-9-