ML17308A122
| ML17308A122 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/25/1990 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17261B111 | List: |
| References | |
| NUDOCS 9007310018 | |
| Download: ML17308A122 (17) | |
Text
ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM
'L~ tt REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9007310018 DOC.DATE: 90/07/25 NOTARIZED: NO DOCKET, g FACXL:50-244 Robert Emmet Ginna Nuclear Plant, Uni 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION Project Directorate I-3
SUBJECT:
Forwards revised EOPs,including Rev 10 to AP-CR.l,Rev 8 to AP-RHR.1,Rev 12 to E-O,Rev 4 to FR-I.3
& Rev 2 to ATT.
DISTRIBUTION CODE:
A003D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR/Licensing Submittal:
Suppl 1 to NURE -0737(G neric Ltr 82-33)
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72)-
05000244 RECXPIENT ID CODE/NAME PDl-3 LA JOHNSON,A INTERNA R
RQ/ HFB11 R
G FILE 01 EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 1
1 RECXPXENT ID CODE/NAME PD1-3 PD OC/LFMB RES/DSIR/EIB NRC PDR COPIES LTTR ENCL 7
7 1
0 1
1 1
1 gq qr a(t'l~>
NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 16 ENCL 15
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//
/I///I//III//I
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zu i'ususzz LAIC 0 II~
ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649.0001 TELEPHONE
- ffEACOOE Tia 546-2700 July 25, 1990 U. S. Nuclear Regulatory Commission Document Control Desk Attn:
Mr. Allen Johnson Project Directorate I-3 Washington, D.
C.
20555
Subject:
Emergency Operating Procedures R.
E. Ginna Nuclear Power Plant Docket No. 50-244 Gentlemen:
As recpxested, enclosed are Ginna Station Emergency Operating Procedures.
Very truly yours, Robert C. Mecred Division Manager Nuclear Production Enclosures xc:
Mr. Robert Gallo, USNRC, Region I Resident Inspector, Ginna Station
'k CJ i@I 90073i00i8 900725 PDR ADOCK 05000244 P
PDC o>>
OP:
P-CR. 1 CONTROL ROOM INACCESSIBILITY REV:
PElof 6
ROCHESTER GAS AND ELECTRIC CORP GINNA STATION CONTROLLED COPY NUMBER TECHNICAL RH IEW POR REVIEW D TE
/
/8" N
SUPERI TE DENT EFFECTIVE D TE QA ON-QA CATEGORY 1.0 REVIEWE BY:
G!NNASTATION START:
TIME CHOMP DATE
a I
0
EOP:
AP-CR.1 CONTROL ROOM INACCESSIBILITY REV:
9 PAGE 2 of 6 A-PURPOSE This procedure provides the step necessary to place'~and maintain the plant in a Hot Shutdown Condition in the event that a control room evacuation is necessary.
B.
ENTRY CONDITIONS/SYMPTOMS 1.
SYMPTOMS The symptoms of CONTROL ROOM INACCESSIBILITY are; a.
Fire in the Control Room, or b.
Smoke in the Control Room, or c.
Noxious Fumes in the Control Room, or d.
Intrusion
t lC IV fi
EOP:
AP-CR.1 TITLE:
CONTROL ROOM INACCESSIBILITY REV 9
PAGE 3 of 6 STBP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED NOTB:
Steps 1 and 2 are immediate action steps.
O 1
Verify Reactor Trip:
o Reactor trip breakers
- OPEN o
MRPI indicates
- ALL CONTROL AND SHUTDOWN RODS ON BOTTOM o
Neutron flux - DECREASING Manual trip the reactor from the control board.
IR the RX can NOT be tripped from the Control Room, THEN locally open the reactor trip breakers.
O 2
Verify Turbine Stop Valves CLOSED Manually trip turbine from MCB.
IP:
turbine can NOT be tripped at the MCB, THEN close both MSIVs.
l pc'
f ikk k'
EOP:
AP-CR.1 TITLE:
CONTROL ROOM INACCESSIBILITY REV:
9 PAGE 4 of 6 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 3 Verify That Fire HAS NOT significantly damaged the MCB Control Circuits o
MCB -
NO FIRE OR FIRE UNDER CONTROL o
Safety related controls and indications -
NO SIGNIFICANT LOSS OP CONTROLS/INDICATION Perform the following actions:
- a. Close both MSIVs.
- b. Trip both reactor coolant pumps.
- c. Close both PRZR relief vlv PCV-430 (431C).
- d. Proceed to the Appendix R locker, immediately outside the Control Room.
- e. Control Room Foreman and communicator proceed to TSC and refer to SC-100 for report requirements.
-1
- f. Implement procedure SC-3.30.1 ALTERNATIVE SHUTDOWN POR CONTROL COMPLEX FIRE.
DO NOT continue in this procedure.
NOTE:
Refer to SC-100, GINNA STATION EVENT EVALUATION AND CLASSIPICATION.
4 Establish Local Operating Stations AS OUTLINED IN ATTACHMENT A 5 Establish AFW. To; The Steam Generators:;
4e.
V
- a. Start - BOTH MOTOR DRIVEN AFW PUMPS>>.
- b. Verify - BOTH PUMPS THROTTLE TO
<230 GPM
- a. Start the TDAFW pump.
Locally open TDAPW pump steam admission valves at the steam header MOV-3504A~ MOV-3505A.
- b. Locally throttle AFW flow.
lg I
4 II f4"'t
EOP:
AP-CR.1 TITLE:
CONTROL ROON INACCESSIBILITY REV:
9 PAGE 5 of r6 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 6 Establish Charging Flow:
- a. Charging pumps - AT LEAST ONE RUNNING
- b. Control charging and letdown-TO MAINTAINPRESSURIZER LEVEL
- a. Start a charging pump.
7 Establish Boration Of The RCS To The Xenon Free CSD Condition:
- a. Refer to 0-3.1 -
POR DETERMINATION OP AMOUNT OP BORIC ACID TO BE ADDED
- b. Start - A BORIC ACID PUMP
- c. Manually open - MOV-350
- d. Stop boration - VHEN REQUIRED BORIC ACID HAS BEEN ADDED 8 Establish Service Water:
o Verify - AT LEAST ONE SERVICE VATER PUMP RUNNING IN EACH LOOP r
Start pumps as necessary.
9 Establish Containment Cooling'i" o Verify,- AT LEAST TWO RECIRC FAN COOLERS: ARE RUNNING Start fans as necessary.
Cr V't
EOP:
AP-CR.1 TITLE CONTROL ROOM INACCESSIBILITY REV:
9 PAGE 6 of 6 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED
- 10. Throttle AFW as necessary-TO MAINTAINS/G LEVELS BETWEEN 774 AND 854 11 Check IF THE CONTROL ROOM IS AGAIN HABITABLE Return to Step 7.
12 Establish Normal Control Room Operations:
- a. Restore
- NORMAL OPERATION OF EQUIPMENT o
Refer to 2.2, PLANT FROM HSD TO COLD SHUTDOVN
-OR-o Refer to ES-0.2, NATURAL CIRCULATION COOLDOVN
-END-
1
AP-CR.1 TITLE:
CONTROL ROOM INACCESSIBILITY REV:
9 PAGE 1 of 1 ATTACHMENT A Duties of Personnel During a Control Room Evacuation SHIFT SUPERVISOR Will direct overall plant operations and recovery actions.
No specific duty station is assigned but the Shift Supervisor should maintain communication with the various groups working to recover from the evacuation.
CONTROL ROOM FOREMAN Will assist the Head Control Operator in transferring equipment to local control, after completion of the transfer the Control Room Foreman will direct the oper-ator's actions to recover the plant.
HEAD CONTROL OPERATOR Will go to Auxiliary Feedwater pump area taking operating procedures "0" book, official records; curve book with him and transfer equipment to local control.
CONTROL OPERATOR Will go to the local operating station in the Charging Pump Room.
PRIMARY AUX OPERATOR-Will go to the local operating stations in the Boric Acid Tank Room.
l SHIFT TECHNICAL ADVISOR Will assist the Head Control Operator while remaining cognizant of plant conditions.
OTHER PERSONNEL-Will assume fire fighting or other duties as directed by the Shift Supervisor or Control Room Foreman.
I'. I