ML20151X012

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Safety Evaluation Re Inservice Testing Program & Requests for Relief
ML20151X012
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 08/16/1988
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20150A869 List:
References
NUDOCS 8808250196
Download: ML20151X012 (11)
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Text

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  1. o UNITED STATES

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3. NUCLEAR REGULATORY COMMISSION hJ\ h/ c k WASHING TO N. D. C. 20555

& y SAFETY EVALUATION REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE INSERVICE TESTING PROGRAM AND REQUESTS FOR RELIEF COMMONWEALTH EDISON COMPANY LASALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NO.: 50-373/374 INTRODUCTION The Code of Federal Regulations,10 CFR 50.55a(g), requires that inservice testing (IST) of ASME Code Class I, 2, and 3 pumps and valves be performed in accordance with Section XI of the ASME Boiler and Pressure Yessel Code and applicable addenca, except where specific written relief has been requested by the licensee and granted l bytheCommissionpursuantto10CFR50.55a(a)(3)(1),(a)(3)(ii),or(g)(6).(i)..In requesting relief, the licensee must demonstrate that (1) the proposed alternatives provide an acceptable level of quality and safety, (2) compliance would result in hardship or unusual difficulties without a compensating increase in the level of quality and safety, nr (3) conformance with certain requirements of the applicable Code edition and addenda is impractical for its facility.

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The Regulation, 10 CFR 50.55a(a)(3)(i), (a)(3)(11), and (g)(6)(1), authorizes the Comission to grant relief from these requirements upon making the necessary  ;

findings. The NRC staff's findings with respect to granting or not granting the relief requested as part of the licensee's IST Program are contained in the Safety Evaluation (SE) issued on the licensee's program. l l

i 8808250196 880816 l PDR ADOCK 05000373 l P PNU

2 The IST progran addressed in this report covers the first ten-year inspection interval from January 1,1984 to January 1,1994. The licensee's program is described in a letter dated July 28, 1987 which supersedes all previous submit-tals. Additional information was submitted in a letter dated October 13, 1987.

The prugram is based on the requirements of Section XI of the ASME Code,1950 Edition through the Winter of 1980 Addenda, and remains in effect until January 1,1994 EVALUATION The IST program and the requests for relief from the requirements of Section XI ,

. have been reviewed by ths staff with the assistance of its contractor, EG&G, Idaho, Inc. (EG&G). In addition, EG&G and staff members met with licensee ,

represent 6tives on June 30 and July 1,1987 in a working session to discuss questions resulting frem the review. The Technical Evaluation Report (TER) provided as Attachment 1 is EG&G's evaluation of the licensee's inservice testing program and relief requests. The staff has reviewed the TER and concurs with the evaluations and conclusions contained in the TER. A summary l

of the pump and valve relief request determinations is presented in Table 1. )

l The granting of relief is based upon the fulfillment of any commitments made by the licensee in its basis for each relief request and the alternative proposed testing.

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Three relief requests were denied (TER sections 3.1.3, 3.7.1 and 4.9.1.2) and seven relief requests were granted with certain conditions (TER sections 4.1.3.1, 4.4.1.1, 4.6.1.1, 4.9.1.1, 4.10.1.1, 4.11.1.1 and 4.11.1.2) . The licensee should refer to the specific TER section for a detailed discussion of these cases. These denials and conditions are listed in TER Appendix C and in addition, Appendix C .

lists other IST program anomalies which were identified during our review.

Relief request RY-35 pertaining to the high pressure core spray testable check valve 1(2)E22-F005 is discussed in TER section 4.4.1.1. Relief is granted from the Code requirements to full-stroke exercise this valve quarterly or at cold shutdowns provided partial-stroke exercising of this v'alve 'is performed at cold shutdowns. However, the licensee is required to full-stroke exercise this valve by disassembly and inspection or some alternative means each refueling outage.

The licensee should n solve all the items listed in Appendix C in accordance with the staff positions. Required program changes should be made within 90 days of receipts of this SER.

INSPECTION l

An inspection of the LaSalle 1 & 2 IST programs should be conducted by Region III.

The inspection should focus on the adequacy of implementing procedures for the IST program, ana satisfactory actions to resolve the items addressed in Appendix C of 1

, the TER. ,

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CONCLUSION

, Based on the review of the licensee's IST program and relief requests, the staff concludes that the IST program as evaluated and modified by this SER will provide reasonable assurance of the operational readiness of the pumps and valves covered by the IST program to perfonn their safety related functions. The staff has ,

detennined that granting relief, pursuant to 10 CFR 50.55a (a)(3)(i), (a)(3(ii),

or (g)(6)(1), is authorized by law and will not endanger life or property, or the comon defense and security and is otherwise in the public interest. In making this determination the staff has considered the alternate testing being implemented, resulting hardships without a compensating increase in safety, or the impracticality of performing the required testing considering the, burden if

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the requirements were imposed. The last column of Table 1 identifies the regu- l 1ation under which the requested relief is granted.

During the review of the licensee's inservice testitig program, the staff has  !

identified certain misinterpretations or emissions of Code requirements. These items are summarized in the TER Appendix C. The IST program for LaSalle 1 & 2, through a submittal dated October 13, 1987, is acceptable for implementation provided that the items noted above are corrected promptly. Relief requests contained in any'su sequent revisions may not be implemented without prior l approval by NRC. l l

Principal Contributor: Y. Li, EMEB: DEST Dated:

O- 's I

l LaSalle County Station,~ Units 1 and 2 '

Table 1 i

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Summary of Relief Requests j i

Relief Alternate ' Relief Request TER Section XI Requirement l Test Action by l Number Section Pump or Valve Number Method USNRC  !

Pump i

RP-01 3.1.1 IWP-3300, Annual-bearing Quarterly Granted / l temperature vibration All pumps in program velocity (g) (6) (1)

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measuraments  !

l I RP-02 3.4.1 IWP-3100, Flow, differential pressure, and inlet pressure Verify Granted /

pressure (g) (6) (1) -

measurement ECCS water leg maintenance pumps 1(2)E22-C003,1(2)E21-C002, i 1(2)E12-C003,1(2)E51-C003 i

! RP-04 3.1.2 IWP-3100 & IWP-4500, Vibra tf or.

Vibration amplitude Granted /

velocity (a) (3) (i)

All pumps in program measurements RP-05 3.2.1 IWP-3100, Inlet pressure Calculate Diesel generator fuel oil Granted /

inlet (g) (6) (1) transfer pumps pressure 00001P,1(2)D001P, 1(2)D002P. ,

RP-05 3.2.2 IWP-3100, Differential Calculate l pressure Granted /  !

Olesel generator fuel oil differential (g) (6; (1) -

pressure'  !

transfer pumps 00001P,1(2)D001P, 1(2)D002P RP-05 3.2.3 IWP-3100, Flow measurement Calculate Diesel generator fuel oil Granted /

flow rate (g) (6) (1) l transfer pumps 00001P,1(2)D001P, 1(2)D002P

RP-06 3.5.1 IWP-3100, Inlet and Measure flow Granted /

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differential pressure and discharge (a) (3) (ii) measurement pressure Standby liquid control pumps i 1(2)C41-C001A and 1(2)C41-C001B I

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Relief Alternate Relief Request TER Section XI Requirement Test Action by Number Section pump or Valve Number Method USNRC RP-08 3.6.1 IWP-4120, Instrument full- Utilize wider Granted /

scale range 3X reference range (g) (6) (1) value instruments P.esidual heat removal pumps, 1(2)E12-C002A,1(2)E12-C0028, 1(2)E12-C002C RP-09 3.3.1 IWP-4120, Instrument full- Utilize wider Granted /

scale range 3X reference range (g) (6) (i) value instruments High pressure core spray pump, .

1(2)E22-C001 ,

RP-10  : L1 IWP-3100, Establish a Duplicate Denied reference pump speed pump flow Reactor core isolation rate and cooling pump, discharge 1(2)E51-C001 pressure RP-11 3.1.3 Table IWP-3100-2, Allowable Utilize the Denied ranges of test quantities guidance from All pumps in the program ANSI /ASME

, GM-6, Oraft 8 Valve RV-06 4.3.1.1 IWV-3300, Positien Verify Granted /

indication -3410, -3520, closure (g) (6) (1)

Quarterly exercising during Reactor feedwater header refueling inboard checks, outage leak 1(2)B21-F010A,-F0108. test Reactor feedwater header -

outboard checks.

1(2)B21-F032A,-F032B ('

RV-10 4.4.2.1 iWV-3522, Quarterly Full-stroke exercising. High pressure Granted / i during (g) (6) (1) '

core spray suppression pool refueling l

, suction check, 1(2)E22-F016 outages i RV-12 4.5.1.1' IWV-3410, -3520, Quarterly Veri fy exercising Granted /

closure (g) (6) (1) t i

Drywell instrument nitrogen during supply header check, refueling 1(2)IN018 outage leak j i

test i I

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Reitef Alternate Relief Request TER Section XI Requirement Test Action by Number Section pump or Valve Number Method USNRC Valve RV-12 4.5.2.1 IWV-3410, -3415, Quarterly exercising, fail.-safe Full-stroke exercise and ggg) testing fail-safe Drywell nitrogen compressor test during drywell suction 1(2)IN001A, refueling 1(2)IN0018 outages Dryer purge isolations, 1(2)IN074,1(2)!N0/5 Orywell inscrument' nitrogen supply,1(2)IN017 -

TIP purge supply, 1(2)INO31 RV-12 4.5.3.1 IWV-3410, -3415, Quarterly Full-stroke Granted /

exercising, fail-safe exercise and (g) (6) (i) testing fail-safe Orywell nitrogen supply, test during 1(2)IN100,1(2)IN101 refueling outages RV-11 4.5.4.1 IWV-3522, Quarterly Full-stroke Granted /

exercising, Orywell nitrugen exercise (g) (6) (1)

, supply checks, during ,

1(2)1N043,1(2)IN044 refueling outages ,

RV-13 4.13.2.1 IWV-3410, Quarterly Full-stroke Granted /

exercising, Standby liquid exercise (g) (6) (1) control pump suctions, during 1(2)C41-F001A,1(2)C41-F0018 refueling outages RV-14 4.13.1.1 IWV-3410, -3520, Quarterly Full-stroke Granted /

exercising, Standby liquid exercise (g) (6) (1)

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control injection check, during 1(2)C41-F007 refueling outages

. RV-14 4.13.3.1 IWV-3520, Quarterly Full-stroke Granted /

exercising, Standby liquid exercise (g) (6) (1) control injection check, during j

1(2)C41-F006 refueling outages

Relief Alternate Relief Requ6st TER Section XI Requirement Test Action by Number $setton Pump or Valve Number Method USNRC Valve RV-16 4.5.4.2 IWV-3522, Quarterly Full-stroko exercising, MSIV and AOS Granted /

exercise (g) (6) (1) accumulator nitrogen supply during checks, 1(2)B21-F024A, refueling

-F0248, -F0240, -F0240, outages

-F0400, -F0400, -F040E,

-F040R, -F040s, -F040V

-F040V RV-17 4.14.1.1 IWV-3410, Quarterly Full-stroke Granted / .

exercising, Containment exercise (g) (6) (1) chilled water supply, during 1(2)VP063A, 0638, 113A, 1138 refueling Containment chilled water outages return, 1(2)VP053A, 0538, 114A, 1148 RV-1B 4.12.1.1 IWV-3520, Quarterly Veri fy exercising, Reactor Granted /

closure (g) (6) (1) recirculation pumps during seal injection refueling '

che.cks, 1(2)B33-F013A, outages

-F0138, -F017A, -F0178

, RV-19 4.1.1.1 IWV-3420 through -3425, Utilize

Granted /
  • containment isolation 10 CFR 50 (a) (3) (1) valves Appendix J, Type C, leak rate testing RV-22 4.7.1.1 IWV-3415, Fall-safe testing, Fail-safe Granted /

MSIVs test during (g) (6) (1) -

1(2)B21-F022A,-F0228, cold

-F022C, -F0220 shutdowns t ,

when the l l drywell is j

de-inerted ,

i RV-25 4.1.3.1 IWV-3417(b),-3523, utilize Granted,

, Corrective action station Tech for those

All valves specs, valves that can be tested quarterly /

(g) (6) (1) ,

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Relief Alternate Relief Request TER Section XI Requirement Test Action by Number Section Pump or Valve Number Method USNRC Valve t

RV-26 4.9.1.2 IWV-3413(b), Stroke time Measure Denied ,

measurements, Control rod stroke time i drive scram discharge volume as a group ,

vents,1(2)C11-F380, -F388, during i Control red drive scram refueling ,

discharge volume drains, outap 1(2)C11-F381, -F389. -

RV-28 4.7.3.1 IWV-3522, Quarterly Manually i exercising, Main steam full-stroke Granted (g) (6) (1/)

relief valve tall pipe exercise -

vacuum breakers during l refueling outages ,

RV-30 4.9.1.1 IWV-3400, -3415, Quarterly Exercise Granted, I exercising and fail-safe during scram .provided testing testing that Control rod scram inlet and stroke i outlet, time is '

1(2)C11-D001-126, -127 addressed /

(g) (6) (1)

RV-30 4.9.2.1 IWV-3522, Quarterly Exercise Granted / '

exercising, Control rod during scram (g) ( 6 ) ('i)  ;

scram discharge header check, testing  ;

1(2)C11-0001-114

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RV-33 4.7.2.1 IWV-3410, Quarterly Full-stroke Granted / l exercising, Automatic exercise (g) (6) (1) l depressurization system during t valve s , 1(2)B21-F013C, refueling '

-F0130, -F013E, -F013R, outages -

-F0135,-F01)U,-F013V RV-34 4.1.2.1 IWV-3411. -3420, -3521, Full-stroke Granted /

Quarterly exercising and exercise and (g) (6) (1) leak rate testing, perform i All excess flow check valves modified leak test during refueling -

i outages in accordance  !

with Tech. i Specs. l l

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Relief Alternate Relief  :

Request TER Section XI Requirement Test 4: tion by ,

Number Section Pump or Valve Number Method ,USNRC Valve RV-35 4.4.1.1 IWV-3412. -3522, Quarterly Partial- Granted I exercising, High pressure stroke provideli core spray testable check, exercise that some 1(2)E22-F005 during cold method is shutdown used to full-stroke each refueling outage /

(g) (6) (1) r RV-35 4.11.1.1 IWy-3412, -3522, Quarterly Partial- Granted, *t exercising, Reactor core stroke Provided >

tsolation cooling testable exercise that some t check,1(2)E51-F066 during cold method to shutdown full-stroke is developed /

(g) (6) (1)

RV-35 4.6.1.1 IWV-3412, -3522, Quarterly Partial- Granted, exercising stroke provided '

Low pressure core : pray exercise that some testable check, during cold method to '

, 1(2)E21-F006 shutdown full-i stroke is

, developed /

(g) (6) (1)

RV-35 4.10.1.1 IWV-3412, -3522, Quarterly Partial- Granted, exercising stroke provided Residual heat remoyal exercise that some testable checkt, during cold method to 1(2)E12-F041A,-F0418.-F041C shutdown full- -

stroke is developed / i (g) (6) (i)

RV-36 4.11.2.1 IWV-3520, Quarterly Partial- Granted /

exercising stroke (g) (6) (1)

Reactor core isolation quarterly and ,

cooling suppression pool full-stroke i suction check, during 1(2)E51-F030 refueling outages l

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t Relief i Request Alternate Relief TER Section XI Requirement Test Number Section Pump or Valve Number Action by Method USNRC Valve RV-38 4.11.1.2 IWV-3412, 3422, Quarterly Partial- Granted, exercising stroke provided Reactor core isolation exercise that some cooling testable check, during cold method to 1(2)E51-F065 shutdowr._ full-

. stroke is developed /

(g) (6) (i)

RV-39 4.2.1.1 IWV-3413(a),-3413(b), Stroke Exercise Granted /

time measurement quarterly (g) (6) (i)

Diesel generator day tank without inlets, 000-004,1(2)D0-004, stroke  ;

1(2)D0-014, timing Diesel fire pump fuel transfer pump inlet 1(2)D0-024 ,

RV-42 .

4.11.1.3 IWV-3410, -3522, Quarterly Exercise open Granted /

exercising quarterly and (g) (6) (1)' l Reactor core isolation verify cooling birometric condenser closure t

vacuum pump discharge, during 1(2)E51-F028, re(ueling Turbine exhaust check, outage leak .

1(2)E51-F040 test i RV-43 4.8.1.1 IWV-3522(b), Exercising

. Manually Granted /

normally closed check valves, full-stroke (a) ( 3) (1) 3 Suppression pool to drywell exercise vacuum breakers, 1(2)PC001A, monthly and 001B, 001C, 0010 measure -

opening force each j

refueling outage L

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