ML17309A224

Advises That Util Meets Regulatory Criteria for Operator Action,Based on Review of NRC 811231 Safety Evaluation of SEP Topic VI-7.B for ESF Switchover & Recalculation of Emergency Procedure E-1.2, Loss of Reactor Coolant.

ML17309A224
Person / Time
Site:	Ginna
Issue date:	02/12/1982
From:	Maier J ROCHESTER GAS & ELECTRIC CORP.
To:	Crutchfield D Office of Nuclear Reactor Regulation
References
TASK-06-07.B, TASK-6-7.B, TASK-RR NUDOCS 8202180136
Download: ML17309A224 (18)

Text

REGULATORY FORMATION DISTRIBUTION S EM (RIDS)

T ItGCE'SSION NBR:8202180136 DOC ~ DATE: 82/02/12 NOTARIZED: NO DOCKET FAG IL: 50-'2QQ Robert Emmet BYNAME G irma Nuc l ear P l an t P UniIt 1P Rochester G 05000244

'AUTH AUTHOR 'AFFILIATION MAIERE J ~ E ~ Rochester Gas L Electric IP ~ NAME RECIPIENT AFFILIATION Corp'E~C CRUTCHFIELDF D ~ Operating Reactor s Branch 5 util I

SUBJECT:

Advises Ithat meets Tregulatory cr i teria for. operator actionibased on review of NRC 811231 safety -evaluation of SEP Topic VI-7,8 for ESF, switchover 8 recalculation of Emergency IProcedure 'E-i.2E "Loss of Reactor Coolant."

DISTRIBUTION CODE: A0388 TITLE: SEP Topics COPIES RECEIVED:LTR ENCL / SIZE: 2 NOTES: 1 copy:SEP Sect. Ldr ~ 050002LILI RECIPIENT  :-COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL LTTR ENCL ACTION: ORB 45 BC Ol 7 7 ID,CODE/NAME'RR/DE/ADAGE INTERNAL: IE 06 2 '2 13 NRR/DE/HGEB NRR/DL/SEPB 10 12 2

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t ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E. MAIER TKt.KPllONK Vice President ARKA COOK jld 546.2700 February 12, 1982

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Director of Nuclear Reactor Regulation g

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Attention: Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

SEP Topic VI-7.B, ESF Switchover R. E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Crutchfield:

Rochester Gas and Electric has reviewed the NRC draft safety evaluation report, for the systems review of SEP Topic VI-7.B, "ESF Switchover", transmitted by letter dated 12/31/81 for Dennis M.

Crutchfield to John E. Maier. We have also reviewed our Emergency Procedure E-1.2, "Loss of Reactor Coolant", to verify the accuracy of the NRC evaluation. One difference noted is that, at 31% RWST level, the operator is to stop only one SI and one CS pump, but not to stop any RHR pumps.

Based on these reviews, RG&E has recalculated the time available for the operator to perform critical ESF Switchover actions, and concluded that the "one-minute-per-action" criterion can be met with the present procedure. This analysis is presented in the attachment. The fact that the RG&E system meets this criterion does not, however, imply that, we believe this time interval to be proper. Given the simple nature of the procedural actions, and the placement of control switches on the control board, we believe that the entire switchover can be completed in less than five minutes (as specified in the procedure). We suggest that, during the Integrated Assessment meeting to be scheduled at Ginna Station, the Integrated Assessment, Review Team verify the timing of the ESF Switchover procedure by observing a walkthrough of the procedure by the operators, if deemed necessary.

It is thus concluded that the Ginna'lant, meets the regulatory criteria for operator action provided in the draft SER for this topic.

8202180i36 820212 PDR ADOCK 05000244

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ROCHESTER GAS AND ELECTRIC RP. SHEET NO.

February 12, 1982 Mr. Dennis M. Crutchfield Rochester Gas and Electric is also at, the present time conducting a review of expected post-accident, flow rates and available pump NPSH. Based on preliminary results, it appears that runout'flow rates for the Safety Injection, Residual Heat Removal, and Containment Spray pumps are less than those used in the analysis (yet substantially higher than the minimum reguirements used in the ECCS analysis). These reduced flow rates would result in longer time periods available to the operator to take critical switchover actions.

Rochester Gas 6 Electric has also reviewed the October 26, 1981 NRC evaluation of the electrical portion of this topic review.

In that review, the NRC concluded that redundant, RWST level indication should be provided. RGK concurs with that conclusion, and will install a second qualified RWST level transmitter.

Thus, there will exist redundant level transmitters, level indication, and level alarms.

completed by September, It is expected that this modification can be 30, 1982.

Very truly yours, J E. Maier Enclosures

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Attachment:

Evaluation of Operator Action Times Available to Perform Critical Post-LOCA ESF Switchover Functions

1. Shut Off 0 eratin Pum s at 10'WST Level Indication Assuming that two SI, two RHR, and one CS pump is operating at 10% level, flow rate's 550 z 2 + <<2000 x 2 + 1615 = 6715 gpm Volume at 10% is 34250 gallons OPERATOR ACTIONS:

Remaining Time Action RWST Volume Remainin Flow 1 minute Shut off 1 SI pump 27535 gal. 6165 gpm 2 minutes Shut. off 2nd SI pump 21370 gal. 5615 gpm 3 minutes Shut off CS.pump 15755 gal. 4000 gpm 4 minutes Shut off 1 RHR pump 11755 gal. 2000 gpm 5 minutes Shut off 2nd RHR pump 9755 gal. 0 Thus, 9755 6165 = 3590 gallons would remain in the RWST above the RWST outlet nozzles.

2. Re-establish ECCS Flow 2A. Calculate available water inventory available for boil off, without fuel assembly uncovering (see Enclosure 1).

From Ginna reactor vessel drawing, it 235 ft~ of water is available above the core.

is estimated that This corresponds to an energy total of 235 ft f 212 h 212

- hf 100 235 ft~ 59.8 ibm) 1150 68 Btu Ibm 1.52 z 10~ Btu 2B. Decay heat at 30 minutes, based on the ANS decay heat curve (without the additional 20% margin).

(1.67%) (1520 Mwt) (3413 x 10 Btu/hr/Mwt) = 8.66 z 10 Btu hr

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Primary and Secondary Volumes Reactor Vessel Volume cu. ft.

Upper Head (Dome) 294.1

.Upper Plenum 634.7 Core (142 in.) 317.1 Lower"Plenum 533.2 Downcommer 654-4

~LOS S Hot Leg 77-6 Cross Over Leg 139.4 Cold Leg 46-9 Reactor Coolant Pump 192 Pressurizer 800 HZP 217.0 liquid HFP 393.3 liquid Surge line 12 '

Steam Generator Inlet Plenum 141.6 Outlet Plenum 141.6 Tubes 644 '

Steam Side 4,579 HZP 2,821 water . 1,758 steam HFP 1,681 water 2,898 steam 1

"A" S.G. to MSIV 776 "B" S.G. to MSIV 1,055 MSIVs plus 36 in. header 223-9 36 in. header to stop valve s389.9 36 in. header to stop valve 288.5

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When the refueling water storage tank low level alarm is actuated at 31X, stop one safety injection pump and one containment spray pump.

Stop auxiliary feedwater flow to the steam generators Men the level has increased to 40'.

).8.6 If a chaxcoal filter high temperature alarm is actuated, open the charcoal filter dousing valves 875A, B or 876A, B.

f.S.7 Restore Service Water Flow to both component cooling water heat exchangers, i.f lost, by openus MOV 4616 an d 4735 for "A" Hx and MOV 4615 and 4734 for "8" Hx l and start both component cooling mter pumps.

3.8.7.1 En sure that the component cooling system's supply and return lmes assoc-iated with containment usexs are isolated from the outs'o system by closing or ensuring closed the following remote operated C.I.

valves.

3.8.7.2 Close supply lines K)V 817 (Common CC supply to Containment)

MOV 749A (CC supply to "A" RCP)

'OV 7498 (CC supply to "8" RCP)

MOV 813 (CC supply to Reactor Support Coolers) .

3.8.7.3 Close return lines tGV 759A (CC return from "A" RCP)

MOV 7598 (CC return from "8" KCP) 4 AOV 745 (CC return from Excess Letdown Heat Exchanger)

MOV 814 (CC ret~ &om Reactor Support Cooler)

NOTE: Valves 813 and 814 isolate autanatically 3.8.8 Ensure that component cooling Bow is established to the residual beat exchangers by opening MOV-738A and MGV 738B CGl from RHR Heat Exchanger.

'I 3.8.9 Verify that component cooling low Q.ow alarms to the res>dual heat removal, contaiztnent spray ard safety injection pumps are not actuated.

3.8.9.1 Alarm A-9 RHR Bmp Cooling Water Outlet low flow.

3.8.9.2 Alarm A-14 Safety Injection Pumps Cooling Water Outlet low flow.

3.8.9.3 Alarm A-6 Containment Spray Pumps Water Outlet low flow.

3.8.10 Determine by PR-420 if reactor coolant system pressure will pexnit recirculation without the use of a high head injection pump {system pxes-sure below 140 psig) ~

2C. Time available to re-establish ECCS flow (1.52 x 10~ Btu) / 8.66 x 10~ Btu hr

= .175 hr = 10.5 minutes 2D. Operator. Actions Required to.Perform ECCS Alignment per E1.2 (see Enclosure 2).

Close Valve 896A Close Valve 896B Close Valve 897 Close .Valve 898 Close Valve 704A Close Valve 704B Open'Valve 850A

, Open Valve 850B Start RHR Pump 1A Start RHR Pump 1B At 1 minute per action, including valve travel times and pump start times, the above sequence would require 10 minutes and 10 seconds to get both trains in service.

Elapsed 1 2 3 4 5 6 7 8 9 10 11 12 Time 896A 896B 897 898 704A 704B 850A 850B Pump lA Pump 1B l 10 minutes,10 seconds

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E-l. 2:8 If spray additive has been actuated during the injection phase and spray additive tank level is higher than 401 or if containment pressure is > 30 psig, prepare to ini.tiate recirculation with containment spray.

At 107. in RWST, stop the operating safety injection, containment spray and residual heat removal pumps, proceed to the recirculation phase.

Recirculation Phase Important: THE PTETCHOVER SHOULD BE COMPLETED AS RAPIDLY AS KSSXBLE (WXTHXN 5 MINUTIA), SXNCE DURING THIS TIME THE CORE IS NOT RECEIVE ANY BfERGENCY COOLING IIATAER. 'DDITIONAL PRECAUTION: If at any time during the Recirculation Phase of the accident offsite power is lost, start at the beginning of the Recirculation Phase of this procedure and reverify and start equipment as necessary after Emergency Diesel Generators tie into their respective buses.

In the event that failure(s) of ECCS equipment or other conditions lead to inadequate fuel cooling notify authorities per SC-1.4 General Radiation Emergency, using telephone. numbers in SC-1.3A.

In the event of inadequate fuel cooling refer to E-l.5 Void Foxmation in the RCS for appropriate additional operations.

Verify the valve status and align valves as follows for recirculation using the RIR pumps.

VERXFY THAT THE FOLLO'TlNG MOV VALVES ARE CLOSED:

826A Boric Acid Storage Tank to Safety Injection Pumps 826B Boric Acid Storage Tank to Safety Injection Pumps 826C Boric Acid Storage Tank to Safety Injection Pumps 826D Boric Acid Storage Tank to Safety Injection Pumps 857A RHR Pumps to Safety Injection Pumps 8 Containment Spray Pumps 857B RHR Pumps to Safety Injection Pumps 8 Containment Spray Pumps 857C RHR Pumps to Safety Injection Pumps 6, Containment Spray Pumps 1813A RCIZ Pump Suction from Sump B 1813B RCIZ Pump Suction from Sump B 700 RCS to BFR pump suction 701 RCS to RHR pump suction 720 RHR Discharge to RCS 721 RHR Discharge to RCS CLOSE THE FOLLOWING MOV'S AND AOV'S

'%96A, RWST to SI Pumps 896B, %1ST to SI Pumps

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FJBOW.'(. 2 gus' P g.+/~op Coo c A-47 MZE: To close 896 A or B the D.C. power hold switch labeled 896A or B 'KEY S<JITCH" must be placed in the "ON" position. After placing valve in proper position return key m8.tch to 'OFF".

%97 SI Pumps Recirculation to RWST

%98 SI Pumps Recirculation to RWST

%04A RHR Pump "A" Suction Cross-Tie

%04B RHR Pump "B" Suction Cross-Tie VERIFY THAT THE FOLIOWING N3V VALVES ARE OPEN:

852A RHR Discharge to Reactor Vessel 852B RHR Discharge to Reactor Discharge 878B Safety Injection Pump Discharge Loop B Cold Leg 878D Safety Injection Pump Discharge Loop A Cold Leg 851A RHR Bmp Suction from Sump B Inside Containment 851B RHR Pump Suction from Sump B Inside Containment 1815A 1C Safety Injection Pump Suction Valve 1815B 1C Safety Injection Pump Suction Valve 825A Safety Injection Pumps Suction from RUST 825B Safety Injection Pumps Suction from RWST 3.8. 1'5 %PEN THE P3LLOWINQ MOV:

~~83.8. 15. 1 850A and 850B RHR Pump Suction From Sump B Outside Containment 3.8.16 Low Head Recirculation 3.8.16.1

~ ~ ~ Start lA and lB residual heat removal pumps.

3.8.16.2 Check flow meter FI-626 to ensure that low head recirculation is adequate.

If FI reading is not at least 400 gpm, switch to high head recirculation.

Refer to Step 3.8.18.

3.8.16.3 Close tDV 856, RUST to BHP. Suction. To operate 1DV 856, J'Z power must be restored at the motor control center (breaker 10C MCC 1C).

3.8.16.4 The Allowing could be indications of passive failure in the low head recirculation path:

Abnormal Q.ow on FI-626.

Flow on FI-931A or FI-931B.

High water level alarm in auxiliary building sump.

High radiation level alarms in the auxiliary buildir g.

NOZE: By exercising HCV-624, and HCV-625, and by watching the corresponding indications on FI-626, FI-931A and FK-931B, the operator should detect the failure location, isolate it, and use an alternate path for recirnQation.

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