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 FAGIL:50-'2QQ Robert Emmet G irma Nuc l ear P l an t P UniIt 1P Rochester G

'AUTH BYNAME AUTHOR 'AFFILIATION MAIEREJ ~ E ~

Rochester Gas L Electric Corp'E~C IP ~ NAME RECIPIENT AFFILIATION CRUTCHFIELDF D ~

Operating Reactor s Branch 5

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SUBJECT:

Advises Ithat util meets Tregulatory cr iteria 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."

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~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E. MAIER Vice President TKt.KPllONK ARKA COOK jld 546.2700 February 12, 1982 Director of Nuclear Reactor Regulation 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

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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.

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ROCHESTER GAS AND ELECTRIC RP.

February 12, 1982 Mr. Dennis M. Crutchfield SHEET NO.

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.

It is expected that this modification can be completed by September, 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:

Time 1 minute 2 minutes 3 minutes 4 minutes 5 minutes Action Shut off 1 SI pump Shut. off 2nd SI pump Shut off CS.pump Shut off 1 RHR pump Shut off 2nd RHR pump Remaining RWST Volume 27535 gal.

21370 gal.

15755 gal.

11755 gal.

9755 gal.

Remainin Flow 6165 gpm 5615 gpm 4000 gpm 2000 gpm 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 is estimated that 235 ft~ of water is available above the core.

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 Upper Head (Dome)

.Upper Plenum Core (142 in.)

Lower"Plenum Downcommer Volume cu. ft.

294.1 634.7 317.1 533.2 654-4

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

Steam Generator Inlet Plenum Outlet Plenum Tubes 141.6 141.6 644 '

Steam Side HZP HFP "A" S.G. to MSIV "B" S.G. to MSIV MSIVs plus 36 in. header 36 in. header to stop valve 36 in. header to stop valve 4,579 2,821 water

. 1,758 steam 1,681 water 2,898 steam 1

776 1,055 223-9 s389.9 288.5

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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 f.S.7 3.8.7.1 If a chaxcoal filter high temperature alarm is actuated, open the charcoal filter dousing valves 875A, B or 876A, B.

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

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

valves.

3.8.7.2 3.8.7.3 3.8.8 3.8.9 3.8.9.1 3.8.9.2 3.8.9.3 3.8.10 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).

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

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

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

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

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)

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2C.

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

=.175 hr = 10.5 minutes hr 2D.

Operator. Actions Required to.Perform ECCS Alignment per E1.2 (see ).

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 Time 896A 896B 897 898 704A 704B 850A 850B Pump lA Pump 1B 1

2 3

4 5

6 7

8 9

10 11 12 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

'DDITIONAL BfERGENCY COOLING IIATAER.

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.

VERXFY THAT THE FOLLO'TlNG MOV VALVES ARE CLOSED:

826A 826B 826C 826D 857A 857B 857C 1813A 1813B 700 701 720 721 Boric Acid Storage Tank to Safety Injection Pumps Boric Acid Storage Tank to Safety Injection Pumps Boric Acid Storage Tank to Safety Injection Pumps Boric Acid Storage Tank to Safety Injection Pumps RHR Pumps to Safety Injection Pumps 8 Containment Spray Pumps RHR Pumps to Safety Injection Pumps 8 Containment Spray Pumps RHR Pumps to Safety Injection Pumps 6, Containment Spray Pumps RCIZ Pump Suction from Sump B

RCIZ Pump Suction from Sump B

RCS to BFR pump suction RCS to RHR pump suction RHR Discharge to RCS RHR Discharge to RCS CLOSE THE FOLLOWING MOV'S AND AOV'S Verify the valve status and align valves as follows for recirculation using the RIR pumps.

'%96A, RWST to SI Pumps

896B,

%1ST to SI Pumps

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%04B 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".

SI Pumps Recirculation to RWST SI Pumps Recirculation to RWST RHR Pump "A" Suction Cross-Tie RHR Pump "B" Suction Cross-Tie VERIFY THAT THE FOLIOWING N3V VALVES ARE OPEN:

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

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%PEN THE P3LLOWINQ MOV:

850A and 850B RHR Pump Suction From Sump B Outside Containment 3.8.16 Low Head Recirculation 3.8.16.1

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3.8.16.2 Start lA and lB residual heat removal pumps.

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 NOZE:

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 buildirg.

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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