ML20237L524

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Safety Evaluation Supporting Util 831109,840629 & 850702 Responses to Generic Ltr 83-28,Items 2.1 & 4.5.2 Re Equipment Classification & Vendor Interface & Reactor Trip Sys Reliability, Respectively
ML20237L524
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 09/01/1987
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20237L513 List:
References
GL-83-28, NUDOCS 8709080440
Download: ML20237L524 (4)
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l SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULAT RELATED TO GENERIC LETTEP 83-28, '

ITEM 2.1 (PART 1) AND ITEM 4.5.2 JAMES A. FITZPATPICK NUCLEAR POWER PLANT DOCKET NO. 50-333 ,

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INTRODUCTION On February 25, 1983, both of the scram circuit bqeakers at Unit 1 of the Salem Nuclear Power Plant failed to open upon an automatic reactor trip signal from the reactor protection system. This incident was terminated manually by the operator about 30 seconds after the initiation of the automatic i trip signal. The failure of the circuit breakers was determined to be related.

to the sticking of the undervoltage trip attachment. Prior to this incident, on February 22, 1983, at Unit 1 of the Salem Nuclear Power Plant, an automatic trip signal was generated based on steam generator low-low level during plant start-up. In this case, the reactor was tripped manually by the operator almost coincidentally with the automatic trip.

[ Following these incidents,.on February 28, 1983, the NRC Executive Director

! for Operations (EDO), directed the staff to investigate and report on the

} generic implications of these occurrences at Unit 1 of the Salem Nuclea'r. Power f Plant. The results of the staff's inquiry into the generic implications of L the Salem unit incidents are reported in NUREG-1000. " Generic Implicat!ont of i the ATWS Events at the Salem Nuclear Power!Mant." As a result of this

! investigation, the Consnission (NRC) requested (by Generic Letter 83-28 dated July 8,1983 ) all licensees of operating mctors, applicants for an operating license, and holders of constructioit permits to respond to generic issues raised by the analyses of these two'ATKS events. L ThisreportisanevaluationoftheresponiessubmittedbythePowerAuthority l

of the State of New York (PASNY), licensee for the James A. Fit $atrick Nuclear Power Plant, for Item 2.1 (Part 1) and Item 4.5 7.of Generic Letter 83-28. A list of the documents reviewed as part of this ehluation is provided a* the end of the report.

Item 2.1 (Part 1) requires licensees t6 confirm chat all Reactor Trip System (RTS) components are identified, classified and treated as safety.-related as indicated in the following statement from Seneric Letter 83-28:

" Licensees and applicants shall confirm that all components whose functioning is required to trip the reactor are identified as safety-related on documents, procedures, and information handling systems used in the plant to control safety-related activities, including ,

maintenance, work orders, and parts replacement."

B709080440 870901 PDR ADOCK 05000333 P PDR ,

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Item 4.5.2 requires licensees with plants not currently designed to permit j

> on-line testing of the RTS, to justify not making provisions for such  !

testing. Alternatives to on-line t-"ing will be considered if the objective i of high reliability can be met in some other way. This review will: I

1. Confirm that the licensee has identified those portions of the RTS that cannot be tested on-line. If it is verified that the entire RTS can be tested on-line, with the above exceptions, no further review is required.

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?. Evaluate modifications proposed by the licensee to permit on-line testing against the existing criteria for design of protection systems.

3. Evaluate proposed alternatives to on-line testing of the RTS where

. modifications necessary to permit on-line testing are impractical.

EVALUATION

1. _ Item 2.1 (Part 1)

We have reviewed the licersee's responses to the requirements of Item P.13 (Part 11 as grovided by submittals dated November 9, 1983', June 29, 1984 , and July 2, 1985 . The licensee stated in these submittals that a review was conducted to verify that all components required to perfom the reactor trip function were classified as safety-related (QA Category 1) equipment. The licensee further stated that a review was performed of the documents, procedures, and information handling systems used to control safety-related activities. The licensee's program does not require that documents such as vendor manuals and drawings be classified as safety-related nor does it requires explicit identification of reactor trip. components as safety-related on these documents. The program does, however, control information handling systems and plant documentation such as procedures, work orders, and procurement documents via the Quality Assurence Program, or requires that they be identified as safety-related and be reviewed by the Plant Operations Review Committee prior to use.

2. Item 4.5.2 Wehavereviewedthelicensee'sresponsestoghereouirementsofjtem4.5.2as provided by submittals dated November 9, 1983 , and June 29, 1984 . In these responses, the licensee stated that the RTS, with the exception of the backup scram valves, is designed to allow on-line testing, and that such tests are performed at the frequencies defined in the Technical Specifications. On-line testing of the backup scram valves will not be performed during plant operation the logic isbecause arranged there suchisthat onlythe one pair of backup repositioning (scram sole..oid energizing) of eithervalves and backup scram solenoid will cause a plant scram. These valves, however, will be independently tested during each refueling outage.

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'f 3 CONCLUSI0)!

I.- Item 2.1 (Part 1)

We find that the above referenced submittals by the licensee confirm that a program exists for identifying, classifying, and treating components reouired for the reactor trip function as safety-related. .While the licensee's program does not require explicit identification of safety-related components in all documents, we find that the described administrative controls which require all

. safety-related activities to be identified, are acceptable. Therefore, the licensee meets all requirements of Item 2.1 (Part 1) of Generic Letter 83-28.

2. Item 4.5.2' We find that the RTS at FitzPatrick, with the exception of the backup scram valves, is designed to permit on-line testing, and that the licensee's justi-fication for not performing on-line testing of the backup scram valves is acceptable. Therefore, the licensee meets all requirements of Item 4.5.2 of

. Generic letter 83-28.

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1-REFERENCES

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A 1. NPCLetterlD.G.EisenhuttoallLicenseesofOperatin9 Reactors, o? ,jjt'c 7' Applicants for Operating License, and Holders;.of Construction Permits,

  • "Reouired Actions Based on Generic Implications'of Salem ATWS Events

, ..j (Generic Letter 83-28),'* July 8.1983. -

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Letter J. P. Bapne, Power Authbrity of the. State of New York, to~

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D. B.'Vassallo,~4RC, November 9, 1983.. .

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y r i Letter, J. P. Bayne, Power' Authority of the State of.New York, to c.

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G4
e. OsJB. Vassa11os,.HRO, June 294- 1984.

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oI Letter, J. P. Bayre, Power Authority of the State of New York, to )[. N' fr;((IV- . 14.D. B.'Vassallo, NRCi July 2, 1985.... \

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