ML20151Z108

SER Supporting Util Response to Generic Ltr 83-28,Item 1.2 Re post-trip Review (Data & Info Capability)

ML20151Z108
Person / Time
Site:	Hope Creek
Issue date:	02/03/1986
From:	NRC
To:
Shared Package
ML20151Z104	List: ML20151Z100 ML20151Z108
References
GL-83-28, NUDOCS 8602140018
Download: ML20151Z108 (11)

Text

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,. H ENCLOSURE SAFETY EVALUATION REPORT FOR GENERIC LETTER 83-28,-ITEM 1.2 . POST-TRIP REVIEW (DATA AND INFORMATION CAPABILITY)

POPE CREEK GENERATING STATION DOCKET NO.: 50-354 I. INTRODUCTION On February 25, 1983, both of the scram circuit breakers at Unit 1 of the Salem Nuclear Power Plant (SNPP) failed to open upon an automatic reactor trip signal from the reactor protection system. This incident occurred during the plant start-up and the reactor was tripped marually by the operator abcut 30 seconds after the initiation of the automatic trip' signal.

The failure of the circuit breakers has beer determined to be related to the sticking of the under voltage trip attachment. On February 22, 1983, during start-up of SNPP,. Unit I, an automatic trip signal occurred as the result of steam generator icw-low level. 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. The results of the staff's inquiry into these incidents are reported in NUREG-1000, " Generic Implications of ATWS Events at the Salem Nuclear Power Plant." As a result of this investigation, the Commission requested (by Generic Letter 83-28 dated July 8,1983) all licensees of operating reactors, applicants for an g2Qh A

O operating license, and holders of construction permits.to respond to certain generic concerns. These concerns are categorized into four areas: (1)

Post-Trip Review, (2) Equipment Classification and Vendor Interface, (3)

Post-Maintenance Testing, and (4) Reactor Trip System Reliability Improvements.

The first action item, Post-Trip Review, consists of Action Item 1.1, "Progran Description and Procedure" and Action Item 1.2, " Data and .

Information Capability." Thissafetyevaluationreport(SER) addresses Action Iten 1.2 only.  !

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11. PEVIEW GUIDELINES i The fo11 ewing review guidelines were developed after initial evaluation of the varicus utility responses to Item 1.2 of Generic Letter 83-28 and incorporate the best features of these submittals. As such, these review l ' guidelines in effect represent a " good practices" approach to post-trip 1

review. We have reviewed the applicant's response to item 1.2 against these j- guidelines:

A. The equipment that provides the digital sequence of events (SOE) record and the analog time history records of an unscheduled shutdown should provide a reliable source of the necessary information to be used in the post-trip review. Each plant variable which is necessary to determine -

I the cause and progression of the events following a plant trip should be 1

4 monitored by at least one recorder (such as a sequence-nf-events recorder or a plant process computer) for digital parameters; and strip 1

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charts, a plant process computer or analog recorder for analog (time history) variables. Performance characteristics guidelines for SOE and time history recorders are as follows:

Each sequence of events recorder should be capable of detecting and recording the sequence of events with a sufficient time discrimination capability to ensure that the time responses associated with each monitored safety-related system can be ascertained, and that a determination can be made as to whether the time response is within accaptable limits ~ based on FSAP Chapter 15 Accident Analyses. The recommended guidelines for the SGE time discrimination is approximately 100 milliseconds. If current SOE recorders do not have this time discrimination capability the licensee should show that the current time discrimination capability is sufficient for an adequate recoastruction of the course of the reactor trip ard post-trip events. As a minimum this should include the ability to adeouately reconstruct the transient and accident scenarios presented in Chapter 15 of the plant FSAR.

Each analog time history data recorder should have a sample interval small enough so that the incident can be accurately reconstructed following a reactor trip. As a minimum, the applicant should be able to reconstruct the course of the transient and accident sequences evaluated in the accident

4 analysis of Chapter 15 of the plant FSAR. .The recommended guideline for the sample interval is 10 seconds. If the time history equipment does not meet this guideline, the applicant should show that.the time history capability is sufficient to accurately reconstruct the transient and accident sequences presented in Chapter 15 of the FSAR. To support the post-trip analysis of the cause of the trip and the proper functioning of involved safety ralated equipment, each analog time history data recorder should be capable of updatino and retaining information from approximately five minutes prior to the trip until at least ten minutes after the trip All equipment used to record sequence of events and time history information should . powered from a reliable and non-interruptible power source. The power source used need not be Class IE.

B. The sequence of events and time history recording equipment should monitor sufficient digital and analog parameters, respectively, to assure that the course of the reactor trip and post-trip events can be reconstructed. The parameters monitored should provide sufficient information to determine the root cause of the unscheduled shutdown, the progression of the reactor trip, and the response of the plant

. parameters and protection and safety systems to the unscheduled shutdowns. Specifically, all input parameters associated with reactor

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trips, safety injections and other safety-related systems as well as 4 output parameters sufficient to record the proper functioning of these systems should be recorded for use in the post-trip review. The

, parameters deemed necessary, as a minimum, to perform a post-trip review that would determine if the plant remaindd within its safety limit 4

design envelope are presented in Table 1. They were selected on the basis of staff engineering judgment following a complete evaluation of utility submittals. If the applicant's SOE recorders and time history recorders do not monitor all of the parameters suggested'in these tables the applicant should show that the existing set of monitored parameters are sufficie't n to establish that the plant remained within the design envelope for the accident conditions analyzed in Chapter 15 of the plant FSAP..

. C. The information gathered.by the sequence of events and time history recorders should be stored in a manner that will allow for data retrieval and analysis. The data may be retained in either hardcopy, (e.g., computer printout, strip chart record), or in an accessible memory (e.g., magnetic disc or tape). This information should be presented in a readable and meaningful format, taking into consideration good human factors practices such as those outlined in NUREG-0700.

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D. Retention of data from all unscheduled shutdowns provides a valuable reference source for the determination of the acceptability of the plant vital parameter and equipment response to subsequent unscheduled

shutdcwns. Infornation gathered during the tcst-trip review is to be retained for the life of the plant for post-trip review comparisons of subsequent events.

III. EVAltlATION AND CONCLUSION By letters dated March 30, 1984, December 17, l'J34, Decenter 16, 1985, and January 24, 1986, Public Service Electric and Gas Company provided inforn:ation regarding its post-trip review prograni data anc information capabilitics fcr Hope Creek Ccr.erating Station. We have evaiuated the applicant's submittals

- against the review guidel r.es cescribed in Section.II. Deviaticrs from the' Guidelines of Sectier II t.ere discussed with representatives of the licensee by telephcne on f,0vember 26, 1985. A brief descripticr. cf the licensee's responses and the staff's evaluation of the resperse 65Lir.st each of the review guidelines follows:

L A. The applicant'has described the perfornance characteristics of. the equipment used to record the sequence of events and tine history data needed for post-trip' review. Based on our review of the applicant's submittals and our telephone conversation, we find that the sequence of events recorder characteristics conform to the guidelines cescribed in Section II A, ar.d are acceptable.

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8. The applicent has established and identified the parsecters to be monitcred and recorded for post-trip review. Cased on our review, we find that the parameters selected by the applicant include'all of those

'i dentified in Table 1 anc ccr. form to the guidelines describcc in Section 11 6'and cre. therefore, acceptable.

C. The applicant described the means for storage and retrieval of the information gathered by the secuence of ever.ts and time history recorders, and for the preser.tatier of this information.for post-trip revitv and analysis. Based on our revier, we find that this information will be presentea in a readable and reaningful format, and that the storage, retrieval and prescntttion confona to the guidelir,es of Section il L.

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D. The applicant's subraittcl of Decerber 16, 1985, indicates thct the cata and inforniation used during post-trip reviews will be retained in an

. accessible manner for thc life of the plant. Based on this infcrmation, we fino that the applicant's program for datt rctehtion conforms to the.

guidelines of Section 11 D, ard is acceptable.

l Based on our review of the applicant's submittals, we conclude that the applicant's post-trip review data and inferrcaticr. capabilities for Hope Creek Generating Station are acceptable.

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i TABLE 1 BWR PARAMETER LIST L

l SOE Time History *

,_ . Recorder . Recorder Parameter / Signal x Reactor Trip x Safety Injection i x Containment Isolation 1

x Turbine Trip i

i x Centrol Rod Position x (1) x Neutron Flux, Power i

i x (1) Main Steam Radiation (2) Containment (Dry Well) Radiation x (1) x Drywell Pressure (Containment Pressure)

(2) Suppression Pool Temperature x.(1) x Primary System Pressure

x (1) x. Primary System level

!" x VSIV Position f

x (1)' Turbine Stop Valve / Control _ Valve i Position I

x Turbine Bypass Valve Position x Feedwater Flow x Steam Flow (3) Recirculation; Flow, Pump Status ,

x (1) Scram Discharge Level x (1) Condenser Vacuum

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SOE . Time History Recorder Recceder Parameter / Signal x AC and DC System Status (Bus Voltage)

(3)(4) Safety Injection; Flow, Pump / Valve-Status x Diesel Generator Status (on/Off, Start /Stop)

(1) Trip parameters (2) Parameter may be recorded by either~an 50E or time history recorder.

.(3): Acceptable recorder options are: .(a) system flow recorded on an SOE recorder,_(b) system flow recorded on a time history r.ecorder, or (c) equipment status recorded on.an SOE recorder.

(4) Ireludes recording of parameters for- all applicable systems from the following: HPCI, LPCI, LPCS, IC, RCIC.-

Mr. C. A. McNeill Public Service Electric & Gas Co. . Hope Creek Generating Station cc:

Gregory Minor Susan C. Remis Richard Hubbard Division of Public Interest Adyncacy Dale Bridenbaugh New Jersey State Department of MHB Technical Associates the Public Advocate 1723 Hamilton Avenue, Suite K Richard J. Hughes Justice Comples San Jose, California 95125 CN-850 Trenton, New Jersey 086?5 Troy B. Conner, Jr. Esquire Office of Legal Counsel Conner'& Wetterhahn Department of Natural Resources 1747 Pennsylvania Avenue N.W. and Environmental Control Washington, D.C. 20006 89 Kings Highway P.O. Box 1401 Dover, Delaware 19903 Richard Fryling, Jr. , Esouire Mr. K. W. Burrowes, Project Engineer Associate General Solicitor Bechtel Power Corporation Public Service Electric & Gas Company 50 Beale Street P. O. Box 570 T5E P. O. Box 3965 Newark, New Jersey 07101 San Francisco, California 94119 Manager - Licensing and Regulation Resident Inspector c/o Public Service Electric & Gas U.S.N.R.C. Bethesda Office Ceester, Suite 550 P. O. Box 241 4520 East-West Highway Hancocks Bridge, New Jersey 08038 Bethesda, Maryland 20814 Ms. Rebecca Green Richard F. Engel New Jersey Bureau of Radiation Deputy Attorney General Protection Division of Law 380 Scotch Road Environmental Protection Section Trenton, New Jersey 08628 Richard J. Hughes Justice Comolex CN-112P Trenton, New Jersey 08625 Mr. Robert J. Touhey, Mr. Anthony J. Pietrofitta Acting Director General Manager DNREC_- Division of Power Production Engineering Environmental Control Atlantic Electric 89 Kings Highway 1199 Black Horse Pike P. O. Box 1401 Pleasantville, New Jersey 08232 Dover, Delaware 19903 Regional Administrator, Region I Mr. R. S. Salvesen U. S. Nuclear Regulatory Commission General Manager-Hope Creek Operation 631 Park Avenue Public Service Electric & Gas Co. King of Prussia, Pennsylvania 19406 P.O. Box A Hancocks Bridge, New Jersey 08038

k Public Service Electric & Gas Co. Hope Creek Generating Station cc:

Mr. B. A..Preston

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., Public Service Electric & Gas Co.

Hope Creek Site MC12Y Licensing Trailer 12LI Foot of Button wood Road Hancock's Bridge, New Jersey 08038 t

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