JPN-92-071, Forwards Section 8, Safe Shutdown Scenario & Timetable, Inadvertently Omitted from Rept, Safe Shutdown Capability Reassessment,10CFR50,App R,Sept 1992. Personnel on engineering-on-shift Position Trained to Be STA

Forwards Section 8, Safe Shutdown Scenario & Timetable, Inadvertently Omitted from Rept, Safe Shutdown Capability Reassessment,10CFR50,App R,Sept 1992. Personnel on engineering-on-shift Position Trained to Be STA

ML20126D235
Person / Time
Site:	FitzPatrick
Issue date:	12/22/1992
From:	Ralph Beedle POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
JPN-92-071, JPN-92-71, NUDOCS 9212240097
Download: ML20126D235 (12)

Text

-

-! 12Diain Sheet ; . . .

s * ' V,tute Plains, New Wrk 10601.

-g7 4'. 914 681 1846

,J A NewYorkPower. - n .,,o . . . ... . :  ;

- 4# Authority ~ .

December 22,1992 -

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JPN-92-0711  :

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, DC 20555

SUBJECT:

James A. FitzPatrick Nuclear Power Plant -

Docket No. 50-333 Fire Protection Program .

Safe Shutdown Scenario and Timetable

References:

' 1. NYPA letter, R. E. Beedle to the NRC, dated October 26,1992, (JPN-92-064) regardire 1992 Safc Shutdown Capability Assessment.

I

2. - NYPA letter, R. E. Beedle to the NRC, dated May 27,1992, (JPN-92-023) regarding the Fire protection improvement Program.

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Dear Sir:

-3

-In Reference 1 the Authority transmitted the 1992 Appendix R assessment of safe -

shutdown capability for the James A. FitzPatrick Nuclear Power Plant. The report titled " Safe -

Shutdown Capability Reassessment,10 CFR 50 Appendix ~ R, September 1992," is the.

technical bases for achieving safe shutdown of the plant'using the criteria in 1.0 CFR 50.48 and Appendix R.

~

In transmitting the report, Section 8, entitled " Safe Shutdown Scenario and Timetable," ,

was not included.-- This letter submits Section 8 and satisfies the Authority's commitments;to :

~_

j complete and submit a new Appendix R model and analysis (Attachment 1,' Items 1.1.1 and -

1.1.6 of Reference 2). As demonstrated by the time lines on Figure 8-1 there is sufficient

- plant staff and time to safely shutdown the plant.-

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9212240097 921222 ~

PDR ADOCK 05000333 ' . i-

-F PDR 3

As discussed in Section 8, AOP-43 uses the Engineer on Shift to monito'r RPV water-level. Personnel in the Engineer on Shift position are undergoing training to become Shift -

Technical Advisors (STAS) to fulfill the Authority commitment to have the STA position be separate from the Shift Supervisor (SS) and the Assistant Shift Supervisor (ASS). As each Engineer on Shift becomes a qualified STA, the Engineer on Shift duties outlined in AOP-43 will be carried out by this STA.

If you have any questions, please contact Mr. J. A. Gray, Jr.

Very truly yours,

<VY Ralph E. Beedle cc: Regional Administrator >

U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA.19406 Office of the Resident inspector U. S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093 Mr. Brian C. McCabe

- Project Directorate I-1 Division _ of Reactor Projects-l/II U. S. Nuclear Regulatory Commission Mail Stop 14 B2 Washington, DC 20555 I

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a. SAFE SHUTT,oWN SCENARIO AND TIMETABLE 0.1 Introduct19D The saf e shutdown scenario and timetable -information provided in this section is based on a worst-case fire af fecting the Control ,

Room (Fire Area VII/ Fire Zone CR-1), the Relay Room (Fire Area VII/ Fire Zone RR-1), the Cable Spreading- Room (Fire Area VII/ Fire Zone CS-1), the Battery Room Corridor (Fire ,

1 Area XVI/ Fire Zone BR-5), or- the North Cable Tunnel (Fire i

l Area ID/ Fire Zone CT-4 ) . This worse-case fire scenario requires the use of an alternative shutdown method independent of th0 Control Room (CR) and as a result imposes the-most significant.

impact on manpower availability for achieving safe shutdown. The equipment and personnel used in this scenario are necessary to achieve hot shutdown in the initial stages of the event. This scenario assumes maximum fire damage and: relies on systems and equipment analyzed to be free from tire damage. Additional personnel will be recalled and will be used for operating safe shutdown equipment and assist in achieving cold shutdown conditions within the' 72 hours required by- 10 CFR SG, Appendix _R, Sections III.G.1.b and III.L.S. The scenario presented in this section'is -integrated into James A. FitzF : trick-Nuclear Power Flant safe shutdown procedures.

0.2 Assumotiong The following assumptions have been made in performing this evaluation:

Page 8-1 i

(1)' The plant is operating-at-100% power upon the occurrence of a fire.

(2) The-reactor trips - either ' automatically or is -- manually tripped frcm the Control Room.

(3) As a limiting condition, loss - of off-site power is assumed with respect to the availability of' components which could be relied on to achieve safe shutdown.

(4) Single failures are not considered.

(5) Spurious operations, with and without of f-site power, directly attributable to the fire are considered.

(6) All equipment required for safe shutdown is assumed to be operational and in service prior to the fire.

(7) All required mechanical components (valves , . etc . ) will remain mechanically operable.

(8) Electrical. power is available to operate safe shutdown components (pumps, MCCs, etc.), except forL those components for which the electrical power supply _ has failed as a result of the fire.

O.3 Activities to be Accomolished Specific operator (s) activities must be performed to' achieve l

stable hot shutdown conditions. Performance of these identified activities prior to exceeding acceptable time limits will ensure' that the plant can be safely shutdown.

After completion of the required initial activities (approximately 30 minutes), additional personnel will become-i available to assist in bringing the plant to cold shutdown-l i

conditions within the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> required by 10 CFR 50, Appendix R, Sections III.G.l.b and III.L.S.

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1-l Page 8-2 i

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Communications required to coordinate the activities necessary to achieve saf e shutdown outside of the Control Room are available.

In addition, 8-hour Appendix R lighting has been--provided to' allow operators to perform their activities.

8.4 Post-Fire Safe Shutdown FSgtures This subsection describes the major f eatures of the _ Alternate Shutdown System. Included in this-description are the, locations and capabilities of-the remote and auxiliary shutdown panels.

8.4.1 Auxiliarv Shutdown Panel 25 ASP-1 Auxiliary Shutdown Panel 25 ASP-1 is located in the' Reactor Building 272' olevation. This panel provides local control capability for the following safe shutdown motor operated valves:

Comnonent Descrintion 10MOV-149B RHRSW to RHR HX B 10MOV-12B RHR HX B Outlet Valve 10MOV-166B RHR HX B Inbound Vent Valve 10MOV-148B RHRSW to RHR HX B 10MOV-70B RHR HX B Steam' Inlet Valve Nuclear Operator C (NOC) will perform the necessary actions required at this panel.

8.4.2 Auxiliarv shutdown Control Panel 25 ASP-2 Auxiliary Shutdown Panel 25 ASP-2 is located ~ in the East l- Crescent stairway, approximately at 245 elevation. This panel provides local control _ capability for the following safe shutdown motor operated valvers:

Page 8 3

Comoonent Descriotion 10MOV-13D RHR Pump D Suction Torus Isolation 10MOV-16B RHR B Min Flow Valve 10MOV-21B RHR B HX Discharge to Torus 10MOV-15D Shutdown Cooling Suction Valve 10MOV-65B RHR B HX Shell Inlet Valve 10MOV-39B Torus B Cooling Isolation Valve 23MOV-60 HPCI Bypass Steam Outboard Isolation Valve 10MOV-27B RHR B LPCI Outboard Injection 12MOV-18 RWCU Outboard Isolation Valve 23MOV-25 HPCI Min Flow to Torus 29MOV-77 MS Line Drain to Condenser Isolation Valve Nuclear Operator B (NOB) will perform the necessary actions required at this panel.

8.4.3 Auxiliary Shutdown PanqLl5 ASP-3 The Auxiliary Shutdown Control Panel 25 ASP-3 is located in the Emergency Diesel Generator B Switchgear Room. This panel provides local control capability for the following safe shutdown components:

Comoonerg Deserintion 10MOV-26B DW Spray Outboard Valve 46MOV-102B ESW Minimum Flow Valve 46MOV-101B ESW B Injection Valve 46P-2B ESW Pump 2B -

71-10614 Normal Supply to Emergency SWGR 71-10602 EDG B Output Breaker 71-10612 EDG D Output Breaker 71-10604 EDG B and EDG D Tie Breaker 71-30660 4160V SWGR Breaker 71-12602 Load Center Supply Breaker .,

10P-1B RHR Service Water Pump Isolation Switch  :

10P-3D RHR Pump Isolation Switch EDG B: Start /Stop, Speed Control, Metering Check, Synchroscope Check, Generator Voltage.

EDG D: Start /Stop, Speed Control, Metering Check, Synchroscope Check, Generator Voltage.

Page 8-4

Either the Senior. Nuclear Operator (SNO) 'or Assistant. Shift

~

Supervisor- (ASS) will perform the necessary actions - required. at this panel (the other person is part of the Fire Brigade).

8.4.4 . Auxiliary Shutdown Panel 25 APP-4 Auxiliary Shutdown control Panel 25 ASP-4 is located outside the Control Room in the Administration Building elevation 300' (adjacent to 25 ASP-5) . This panel allows the operators to isolata the outboard main steam isolation valves (29AOV-86A-D). MSIV position indication is also available on this' panel. This action will be done by the Nuclear Cont rol Operator (NCO) after he has initiated reactor scram.

8.4.5 Auxiliarv Shutdown Panel 25 ASP-5 Auxiliary Shutdown Control Panel 25 ASP-5 is located outside the Control Room in the Administration Building elevation 300' (adjacent to 25 ASP-4). This panel allows the operators to isolate the eleven safety / relief valves (02RV2-71A, B, C, D, E, F, G, H, J, K and L). The Shift Supervisor (SS) will perform this action.

-8.4.6 Remote Shutdow;t Panol 25RSP Remote Shutdown Panel 25RSP is located in the north side of the Reactor Buildint at 300' elevation (next to the ADS Control Panel 02 ACS-071) . This panel-provides local control / indication for the following safe shutdown components:

Page 8-5 e g , ,w -- -

w --

. . . - - _ . _~._ _.. - - . . .- --

t ComDI2n9.nt Descrintion 10P-1B RHRSW B Pump .

10P-3D RHR D Pump

• 10MOV-66B RHR HX B Bypass Valve '

10MOV-25B LPCI Inboard Injection Valve 10MOV-89B RHRSW Discharge Valve 2 ', AOV- 12 9 B N, Instrument Heater Isolation Valve 02AOV-17 Reactor Head Vent '

23MOV-16 HPCI Outboard Steam Supply Valve 27AOV-126B CAD B Inlet Valve 71-11602 Feeder Breaker for Ll6 Switchgear 27TI-101 Torus Water Temperature The Nuclear Control Operator (NCO) will be stationed at this: ,

'r panel. The NCO will also monitor reactor pressure on Rack 25-6

..+

located in the immediate vicinity of this panel. As discussed in AOP-43 and shown in Figure 8-1, the Shift Supervisor (SS) nay ,

initiate actions at this panel until the NCO is available.

8 . 4 . */ Local ADS Control Panel 02 ADS-71 -

Local ADS Control Panel 02 ADS-71 is located on the north side of the Reactor Building at 300' elevation (next to the Remote

!- Shutdown Panel 25RSP). This panel provides local control-capability for safety / valves 02RV2-71A, B, C, D, E, F, G, H ', J, K

'and L.

l- The Shift Supervisor (SS) will be stationed at this panel and -

i-will coordinate safe shutdown activities from this~ location.

1 I.

Page 8-6

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8.4.8 LQsAl DigggL QgngIator Control Emargency Diesel Generators B and D are provided With local control independent of the Control Room. The Control Panels are located in the Diesel Generator Room and in the Emergency Switchgear Room. The control panels provide isolation f rom the control Rcom along with local control, indication, and metering capabilities for the B and D Emergency Diesel Generator and the 4.16kV emergjency bus breakers.

8.4.9 Insirnment RacA__2.5-51 Instrument Rack 25-51 contains a fuel zone reactor vessel level indicator. The Engir eer on Shif t mans this rack and reports changes in reactor vessel level to the Shift Supervisor (SS).

8.4.10 Panel 6 61tV- 3 B Panel 66HV-3B is located on elevation 272' of the Reactor Building. This panel contains isolation switches for the Division B Crescent Area coolers. The Nuclear Operator C (NOC) operates these switches prior to manning 25 ASP-1.

8.4.11 Em2I.gancy Licht.ing As part of the Appendix R reanalysis effort, illumination level and duration testing was perf ormed on areas requiring access and egress to safe shutdown control panels and specific safe shutdown components where operation of the components is necessary.

As a result of this testing, modifications have been performed to achieve compliance with 10 CFR 50, Appendix R, Section III.J as described in Section 7 of this report.

Page 8-7

- .. -. . . . - - . - . . _ _ . - - . _ - - ~ . . ._ . _ - - -

i 0.4.10 Communications >

The emergency-communication-system has been reviewed as part ,

of the recent Appendix R' reanalysis. A communication system has been provided to support-safe shutdown communications.

8.5 Actions Reauired to Achieve shutdown for Fires Recuirina Control Room Evacuatio.n The actions required to achieve stable hot shutdown conditions will-be accomplished with five-operators and an Engineer on Shift. ,

These actions will be accomplished within the first half-hour af ter evacuation of the Control Room. Safe Shutdown activities are identified and described in James A. FitzPatrick ileclear Power Plant Abnormal Operating Procedure AOP-43.

Personnel in the Engineer on Shift position are urde'Joing

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training to become Shift Technical Advisors (STAS) to fulfill the Authority commitment to have the STA position be separate from the Shift Supervisor (SS) and the Assistant Shif t Supervisor ( ASS) . -As each Engineer on Shif t becomes a qualified STA, the Engineer on Shift duties outlined in AOP-43 will be carried out by this STA.

Hot shutdown operator actions will proceed with the primary

-focus of isolating the reactor, establishing a reliable emergency.

l power source and preparing the RHR system for LPCI injection l

operation. Within thty (30) minutes trom the initiation of the ,

I- Appendix R event, required safe shutdown systems and components will be available such that reactor vessel depressurization;and RHR-LPCI injection can be performed (see Section 9.1.10 regarding.

NRC exemption). The rnactor vessel will then be depressurized to Page 8-8 l

allow RHR-LPCI injection. Suppression Pool Cooling will be established by filling the RCS and establishing alternate shutdown cooling. Process mon'toring components have been ensured to be available such that operators can monitor reactor level, reactor pressure, torus level, torus temperature and other cystem variables. Figure 8-1 provides the timeline for activities required to achieve hot shutdown.

0.6 Eqfe Dhutiqwn_PLqngdures for Fires !{ot Requirina Control Room RYnnunt.isn A detailed safe shutdown procedure has been established to ,

address safe shutdown for fire areas not requiring Contrcl Room evacuation. This procedure, in conjunction with plant emergency operating procedures will ensure safe shutdown during a fire in any plant fire area. The detailed procedure is documented in plant Isbnormal Operating Procedure 28 (AOP-28).

Page S-9

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!*' New York Power Authority - James A. FitzPatrick Nuclear Power Plant j 5'*'5 " 5" Figure 8-1 Operator Actions Required to Achieve Safe llot Shutdown Timeline TM[ We WNUTES 0 S to 15 20 25 30 3S eo 45 5 5 I I I I I & I I AFIRE STARTS se THE CONTROL ROOu. RO.AT ROOW OR CAGLE SPREADING ftOCtd I

Arat ACTuArts oETtCTo. AND AciowAnc st-EssoN snTEus i i  : 1 ALOSS OF CrislTE PowtR WAf CCCUR g AREACTOR SCRAM l l [ { l sreE BRCADE ASSEweLES AT 272" ADuwa5TRADON BUILD *C HAdwAv I

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I g A hANUAL SCRAM. IF PE0ufRED iPaTIATE ARs (STEPS C11 AND C.2 2)

AOP-43 I StAISECitON CJ l l [ { ]

(NUCLEAR CONTROL OPERATOR) e TRP MAsN TUR9tNE (STEP C.2 3) I e CLOSE WSNS AT PANELS 09-3 APO 09-4 (STEP C2.4)

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+ PLAct ISOLATION $ WITCHES se LOCAL AT 2SASP-4. VERIFY CLOSED OUTisoAp0 usivs (STEP CO 6) l l

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