ML18100A692

Forwards Preliminary Time Analysis for App R Alternate Shutdown & Time Dependent Operator Actions for Baseline Scenario (Time Analysis),Per App R Insp on 930517-21 & 930530 Telcon

ML18100A692
Person / Time
Site:	Salem
Issue date:	10/07/1993
From:	Thomson F Public Service Enterprise Group
To:	Ruland W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NLR-N93143, NUDOCS 9311150024
Download: ML18100A692 (5)

Text

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• Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department October 7, 1993 NLR-N93143 U.S. Nuclear Regulatory Commission Division of Reactor Safety 475 Allendale Road King of Prussia, PA 19406 Attn: Mr. William H. Ruland Electrical Section Chief

Dear Sir:

10 CFR 50, APPENDIX R INSPECTION PRELIMINARY TIME ANALYSIS FOR APPENDIX R ALTERNATE SHUTDOWN SALEM GENERATING STATION UNITS 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Pursuant to the Appendix R Inspection, conducted from May 17, through May 21, 1993, and a subsequent teleconference between PSE&G and the NRC, dated May 30, 1993, an issue was raised due to a lack of detail in our Salem plant's original time analysis for demonstrating the capability to bring the plant to COLD SHUTDOWN conditions in an acceptable period of time in the event of a fire. To resolve this issue, we have committed to provide a detailed, comprehensive analysis to the NRC. The completion date for this analysis is tied to receipt of an impending license amendment that will permit the boron concentration in the boric acid storage tanks to be reduced -which affects the analysis.

In the interim, however, to promote an increased level of confidence that Salem plant has the capability to achieve safe shutdown within an acceptable time period, we have performed a preliminary analysis using the actual time-dependent operator action times gathered on July 16, 1993, during a simulated performance of our procedure for alternate shutdown from outside the control room and more detailed plant cooldown calculations.

The results of our preliminary analysis are provided in Attachments 1, 2 and Figure 1 for your information.

9311150024 931007 PDR ADOCK 05000272 G PDR The Energy People 95-2168 (87.SM) 12-90 Mr. William H. Ruland NLR-N93143 2 October 7, 1993 Should you have further questions on this matter, we will be pleased to discuss them with you. Sincerely, F. x. Thomson, Jr. Manager -Licensing

& Regulation Attachments c Mr. J. c. Stone, Senior Licensing Project Manager U. s. Nuclear Regulatory Commission One White Flint North MS 14, E-21 11555 Rockville Pike Rockville, MD 20852 Mr. c. Marschall, Senior Resident Inspector U. S. Nuclear Regulatory Commission Altenlate shutdCMn action times for specific tasks delineated in Salem Station Operating Procedure, S1(2) .OP...AB.CR-0002(Q), were gathered during a sinru.lated perfonnance of the procedure on July 16, 1993. 'Ihese times were used as input into the t.ilne analysis.

Attachrnent 2 lists the time-deperrlent operator actions for the first two hours of the postulated event. 'Ihe first two hours are considered to be the time period necessacy to achieve, am stabilize at, HOI' STANDBY corrlitions prior to initiating cooldCMn.

Following this two hour period, eight hours at a cooldCMn rate of 25°F per hour are needed to reach 350°F, Har SHUTIXlWN conlitions.

When the Reactor Coolant System (RCS) terrperature reach.es approximately 350°F, an eight hour thennal soak period is assumed to allow for heat dissipation frcim the vessel upper head prior to depressurization.

After carrpletion of the thennal soak period, a one hour RCS depressurization is initiated in order to reach the corrlitions required to place the Residual Heat Rem::wal (RHR) system in service. Since the cooldCMn from Har SHlJI'[X)WN to CDID SHUl'IXlWN (preliminarily calculated at 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br />) is essentially a function of plant thennal responses, operator action times are not considered lllniting am are, therefore, not included in this analysis.

'Ihe time analysis includes both the :rnininn.nn required actions am discretionary actions such as use of the pressurizer heaters or system lineup verifications (these latter actions are captured under "continue procedure" in Attachment 2 am Figure 1). Only the Technical Specifications (TS) minimum shift crew carrposition" staff is assumed to be available to perfonn the required actions to achieve HOI' STANDBY. For clarity, Figure 1 graphically correlates Attachment 2 operator actions to TS :rnininn.nn staff requirements.

'Ihe figure shows that each shift crew member assigned to the listed equipment/location would be responsible for all actions taken for that equipment/location to achieve Har STANDBY. 'Ihe figure also highlights the point in time where each crew member, having carrpleted all necessary actions at his assigned location, would be available for further discretionary assigrnnents from the SNSS. PSE&G believes that our preli.minai:y time analysis for ti.me-dependent operator actions am conservative cooldown and thennal soak assumptions (totalling 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> for reaching HOI' SHUTOOWN), when added to our preliminarily calculated HOI' SHlJI'[X)WN to CDID SHIJl'OOWN time of 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br /> adequately demonstrates that Salem plant has the capability to achieve safe shutdCMn within the required 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> ti.me constraint.

. *

• Time Depement Operator Actions Far Baseline Scenario (Time Ana1ysis)

Hot stamby Period (0 -2 hwrs) 5 13 22 22 22 22 30 34 39 44 45 -120 cpmitor Actions Assemble At Hot Shutdown Panel Establish Auxiliary Feedwater Flow ('l'ln::bi.ne Driven Pump) C Emergency Diesel Generator loaded Initiate Reactor Coolant PLnrp Seal Injection Flow Close Main steam Isolation Valves Atmospheric steam D.mp Valve Operation Initiate RCP Seal Return B Emergency Diesel Generator loaded A Emergency Diesel Generator loaded Initiate RCS Boration Continue Prtx::edure

-SNSS Discretionary Actions (based on cex>ldown needs) *Time after reactor trip (starting from time= o to em of action time) Cooldcwn Period (start At 2 Bcurs) Hours 2 10 18 19 cpmitor Actions Initiate RCS Cooldown At 25°Fjhour

-Using Atmospheric steam D.mp Valves for steam Generators 11 (21) and 12 (22)

• Hold RCS Cooldown At Approxinlately 350°F For 'lhennal Soak Depressurize To less Than 375 psig For RHR a.it-in Place RHR In Service And Cooldown To 200°F Figure 1 SINGLE UNIT SHUTDOWN ASSIGNMENTS PERSONNEL SRO HSD PANEL STA SWGR OPERATIONS

/ ROVER NCO 1 AFW /eves CONTIWE PROCEDURE

• NCO 2 eves CONTINUE PROCEDURE

• EO 1 (SHARED) Msivs (INBOARD)

/

EO 2 MSIVs (OUTBOARD)

/ PRESSURIZER HEATERS CONTINUE PROCEDURE

• EO 3 EDGs (ALL LOADED) CONTINUE PROCEDURE

• ------------Is'>------------_..

E* (SHARED) PR6 & PR7 / OTHER MOV OPERATIONS CONTIBU!:

PROCEDURE

• 0 5 10 15 20 25 30 40 60 70 80 TIME (MINUTES)

• Beyond procedure continuation includes discretionary actions as required.