IR 05000373/1987004

Safety Insp Rept 50-373/87-04 on 870123.Violation Noted: Failure to Follow 10CFR50,App J Requirements Re Containment Integrated Leak Rate Test

ML20210B507
Person / Time
Site:	LaSalle
Issue date:	01/30/1987
From:	Mendez R, Ring M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20210B483	List: IR 05000373/1987004 ML20210B479 ML20210B490
References
50-373-87-04, 50-373-87-4, NUDOCS 8702090176
Download: ML20210B507 (12)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION III

l Report No. 50-373/87004(DRS)

Docket No. 50-373 License No. NPF-11

Licensee: Commonwealth Edison Company

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P.O. Box 767 i Chicago, IL 60690 Facility Name: LaSalle County Station, Unit 1

Inspection At

Region III Office, Glen Ellyn, IL Inspection Conducted: January 23, 1987 Inspector: R. MendeiM/I //30/57 Date

'TM Approved By: M. A. Ring, Ch f //3 7 Test Programs Section Date

Inspection Summary

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Inspection on January 23, 1987 (Report No. 50-373/87004(DRS))

Areas Inspected: Special safety inspection to followup on an unresolved item previously identified in Inspection Report No. 50-373/86004(DRS).

Results: In the area inspected, one violation was identified (failure to

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follow the requirements of Appendix J, Paragraph 2.A).

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DETAILS Persons Contacted

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Commonwealth Edison Company (CECO)

• T. Hammerich, Technical Staff Compliance

• Denotes personnel present at the telephone conference of January 23, 198 . Followup of a Previously Identified Item During)an (CILRT activitiesinspection of Containment performed in June 1986, Integrated an issueLeak was Rate identified Testing

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requiring NRC resolution as to its enforceability. This issue,

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documented as Unresolved Item 373/86022-02, involved the licensee's failure to line up motor operator valves consistent with 10 CFR 50,

Appendix J requirements and the findings made by NRR during the

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licensing review prior to issuance of the operating license. The inspectors noted, during a review of the valve lineup, procedure, that several valves were lined up in the closed position instead of being open for the CILR Although these valves are not closed by

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an automatic isolation signal, the licensee insisted that credit as containment isolation valves could be taken and therefore, these valves were closed by the licensee during the CILRT. The systems that were in question were the Feedwater and the Reactor Core Isolation Cooling (RCIC) syste The feedwater isolation valves, as listed in the LaSalle FSAR, are 1821-F010A(B), 1821-F032A(B), and 1821-F065A(B). Valves 1821-F010A(B), and 1821-F032A(B) are check valves for which credit is normally taken to ensure containment integrity. Valve 1821-F065A(B) is a motor operated gate valve that is specified in the FSAR as being for "long-term leak tightness only." This valve r is normally open and requires operator action to close the valv A similar situation exists with the RCIC system. The Reactor Core Isolation Cooling Steam Exhaust isolation valves, as listed in the FSAR are 1E51-F040 and 1E51-F068. Valve IE51-F040 is a check valve andIsthevalveforwhichcreditisnormallytakenduringaTypeA test. Valve 1E51-F068 is a gate valve which is normally open, relies upon operator action for closure, and is also for long-term leak tightnes It was the inspector's position that valves 1821F065A(B) and IE51-F068 must be left in the open position for the type A test because the valves are normally open and require operator action to close, i.e., these valves do not close automatically on an isolation signal. Futhermore, the licensee was informed that no containment boundary credit could be taken during the CILRT for the valve This position was substantiated at the time of the CILRT through conversations with the Region III inspector and the NRR Containment

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Branch reviewer involved in the LaSalle preoperational leak test progra This issue was referred to NRR's Division of Boiling Water Reactor Licensing for resolution. By letter dated December 15, 1986,

" Evaluation of Valve Lineup for Type-A Test," NRR responded to the above issue (Attachment A). The letter states in part, "The regulations (10CFRPart50,AppendixJ)requirethecontainmentto be leak tested as close to the 'as-is" condition as practical. For some time now, it has been the staff's interpretation that "as-is" means the valve position for the CILRT should be consistent with the one in a normal operating mode when those valves are remote manual motor-operated... Therefore, the gate valves should be left open for the CILRT." This failure by the licensee to perform a Type A test of the containment in as close to the "as-is" condition as practical is a violation of 10 CFR 50, Appendix J (373/87004-01).

Based on the above, Unresolved Item 373/86022-02 is considered closed and upgraded a to violation (373/87004-01). Based on NRR's conclusion that the gate valves in question should be left open during CILRTs, a penalty must be added to the CILRT which, in this case, resulted in the containment exceeding the allowable as-found CILRT leakage of <0.75 La. The following is a summary of the as-found containment leak rate without valve 1B21-F065A (units are in weight percent per day):

Without Valve Measurement 1821-F065A Penalties incurred due to repairs 0.269 oradjustmentspriortoCILRT CILRT valve lineup penalties 0.042 As-left Type A test results 0.227 Total as-found 0.538 As indicated above, the as-found condition of 0.538 wt.%/ day is greater than the allowed leakage of 0.476 wt.%/ day and exceeds the allowable limit of Appendix J (0.75 La). The licensee failed the CILRT in the as-found conditio . Exit Interview The inspector contacted licensee representatives denoted in Paragraph 1 by telephone at the conclusion of the inspection on January 23, 198 The inspector summarized the scope and findings of the inspection. The licensee acknowledged NRR's position, but expressed concerns regarding the requirement to Type C test valves 1821-F065A(B) and 1E51-F068 as listed in the LaSalle FSAR. Appendix J defines Type C tests as those tests intended to measure containment isolation valve leakage rates. The

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licensee uses this definition to lineup the valves for the Type A test and reguires the isolation valves to be closed during post accident

., conditions. According to the' licensee this is in apparent conflict with NRR's position to have valves F065A(B) and F068 open for the Type A tes The licensee indicated they would communicate their concerns to NRR.

The licensee did not indicate that any of the information disclosed during the inspection could be considered proprietary in natur ,

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, , ATTACIIMENT "A" NUCLEAR REGULATORY COMMISSION

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ggCD Docket No. 50-373 MEMORANDUM FOR: 9ttl J. Paperiello, 91 rector

) Division of Reactor Safety Region III FROM:

Robert M. Bernero, Director Division of BWR Licensing Office of Nuclear Reactor Regulation SUBJECT: REQUEST FOR TECHNICAL ASSISTANCE - REVIEW OF APPENDIX-J TYPE-A TEST AT LA SALLE UNIT 1 - TIA 86-41B In your letter dated August 5,1986, you requested NRR .to document whether the gate valves for the feedline and Reactor Core Isolation Cooling turbine exhaust line should be left open for the Type-A Containment Integrated Leak Rate Test at La Salle. We have completed our revicw and have concluded the valves should be left open. The basis for this conclusion is discussed in the enclosed Safety Evaluation.

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We trust that the information provided is responsive to ynur concerns, and the NRR responsibilities under TIA 86-418 have been complete #

Robert M. Bernero, Director Division of BWR Licensing Office of Nuclear Reactor Regulation

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Enclosure:

As stated go 188

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EVALUATION 0F VALVE LINEUP FOR TYPE-A LEAK TEST LA SALLE COUNTY STATION UNIT 1 C0W40NWEALTHEDISONCOMPANJ D0CKET NO. 50-373 REFERENCE: MEMORANDUM FROM CARL J. PAPERIELLO 0F REGION III TO GARY HO OF NRR, " REQUEST FOR ASSISTANCE-REVIEW LASALLE I TYPE-A TEST VALVE LINEUP", AUGUST 5, 198 .0 INTRODUCTION l It was requested that NRR provide Region III with an evaluation of the licensee's position regarding valvo lineup for the Type-A Containment

! Integrated Leak Rate Test (CILRT) at the La Salle Station. The valves in question are 182B21F065A,B on feedline and IE51-F068 on the Reactor Core IsolationCooling(RCIC)turbineexhaustline.

f EVALUATION

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The valves in question are remote manual motor-operated gate valves and they are normally open in the operating mode. The regulations (10 CFR Part 50, Appendix J) require the containment to be leak tested as close to the "as is" condition as practical. For sometime now, it has been the staff's interpretation that "as is" means that the valve position for CILRT should be consistant with the one in a nonnal operating mode when those valves are remote manual motor-operate The feedwater lines (there are two lines altogether) penetrate the drywell to connect with the reactor pressure vessel. There are three isolation valves per line. The isolation valve inside the drywell is a check valve. Outside the primary containment, there is another check valv Farther away from the containment is a remote manual motor-operated gate valve 182B21F065A,B. Should a break occur in the feedwater line, the check valves would prevent a significant loss of reactor coolant inventory, and would provide prompt primary containment isolatio During the postulated loss-of-coolant accident, it is desirable to maintain reactor makeup water from all sources of supply. For this

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' reason, the outermost gate valve does not automatically isolate upon a signal from the protection system. Therefore, the gate valves should be lef t open for CILRT.

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-t-As noted previously, two check valves offer issnediate isolation should a break occur in the feedwater line. Subsequently, the gate valve is to be remote manually closed from the main control room to provide long-ters leakage protection. For other accidents, the gate valve can be closed once the operator determines that feedwater makeup is unavailable or unnecessary, thus providing long-tern leak tightness as stated in the Final Safety Analysis Report (FSAR).

The gate valve 1E51F068 is on the RCIC turbine exhaust line approximately three feet outside of the containment. The turbine is steam driven and exhaust steam enters the suppression pool. As in the case of the feedline, there is a check valve upstress in relation to the gate valve, and it is used for an issnediate isolation of the containment in case of a break in

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l the line. The gate valve is motor-operated and remote manually actuate It is normally open during plant operation. The FSAR states that "the

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gate valve in the RCIC turbine exhaust is designed to be locked open from f

the control room, and interlocked to preclude opening of the in let steam

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valve to the turbine while the turbine exhaust valve is not in full open

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position". Table 6.2-21 of the FSAR also calls for an open gate valve Therefore, position for a post accident as well as plant normal operatio the gate valve, in question, should be left open for the CILR .0 CONCLUSION Based on the design, functions, and intended operation, we conclude that

the gate valves in question should be left open for the duration of the CILRT. It should be noted that the majority of licensees have conducted i

their CILRT in the past with these valves in the open position. Therefor leaving these valves open, La Salle would be consistent with past industry l

i practice in this regard.

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