ML20213G818

Responds to 870423-0507 Requests for Addl Info Re Fire Protection Safe Shutdown Rept

ML20213G818
Person / Time
Site:	Beaver Valley
Issue date:	05/11/1987
From:	Carey J DUQUESNE LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
2NRC-7-110, TAC-62874, NUDOCS 8705180463
Download: ML20213G818 (7)

Text

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gpt 2NRC-7-110 Telecopyl l Beagr Valgy No. 2 Unit Project organizauon P.O. Box 328 May 11, 1987 Shippingport, PA 15077 United States Nuclear Pegulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

Beaver Valley Power Station Unit No. 2 Docket No. 50-412 Fire Protection Safe Shutdown Report - Responses to NRC Requests for Additional Information Gentlemen:

In telephone conferences from April 23 through May 7, 1987, between '

Duquesne Light Company (DLC) representatives and NRC/NRR Plant Systems Branch reviewer, Mr. R. Goel, DLC was requested to provide additional information related to the Fire Protection Safe Shutdown Report. In accordance with Mr.

Goel's request, the attachment to this letter provides the formal documentation of DLC's responses.

DUQUESNE LI T COMPANY a

" JR y. Carey ff 5 Senior'T/ ice PresiUent JD0/ijr NR/JD0/FP/SHTDN Attachment AR/NAR cc: Mr. P. Tam, Project Manager (w/a)

Mr. J. Beall, NRC Sr. Resident Inspector (w/a)

Mr. L. Prividy, NRC Resident Inspector (w/a)

Mr. William T. Russell, NRC Region I Administrator (w/a)

INP0 Records Center (w/a)

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r United States Nuclear Regulatory Commission Fire Protection Safe Shutdown Report - Responses to NRC Requests for Additional Information Page 2 COMMONWEALTH OF PENNSYLVANIA )

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COUNTY OF BEAVER On this ,// day of h M

, / ' , before me, a Notary Public in and for said Commor[dealth and County, personally appeared J.

J. Carey, who being duly sworn, deposed' and said that (1) he is Senior Vice President of Duquesne Light, (2) he is duly authorized to execute and file the foregoing Submittal on behalf of said Company, and (3) the statements set forth in the Submittal are true and correct to the best of his knowledge.

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FIRE PROTECTION SAFE SHUTDOWN REPORT RESPONSES TO NRC REQUESTS FOR ADDITIONAL INFORMATION

1. NRC Request Provide documentation to show that power is removed from the RHR suction valves when appropriate RCS pressure is reached.

Response

DLC provided the requested documentation via express mail on April 27, 1987. This information consisted of Beaver Valley Power Station (BVPS)

Operating Manual (0M) Section 2.50.4, " Instructions to Heat Up Reactor Plant from Cold Shutdown (Tavg Less Than or Equal to 200*F) to Hot Shutdown (Tavg Greater Than 200*F and Less than 350*F) with the Turbine Plant Isolated", Issue 1/Revison 2, Pages G1 through G7, and BVPS OM Section 2.10.4, " Residual Heat Removal System Shutdown", Issue 1/ Revision 2, Pages C1 through C3. OM-2.50.4, Instruction No. 31, refers to 0M-2.10.4 which documents power removal from the RHR suction valves.

2. NRC Request Indicate whether compressed air is needed for alternate shutdown.

Response

Compressed air is needed for alternate shutdown.

3. NRC Request

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Provide documentation to demonstrate that required response times for operator actions during safe and alternate shutdown are met.

Response

DLC provided a documented time study via express mail on April 27, 1987.

This time study is for alternate safe shutdown from outside the control room and is based on a February 5,1987, walkdown. Attached to the time study was a discussion on the required time to operate major components used to achieve safe shutdown versus actual operator time. The time study demonstrates that required response times for operator actions are met.

The required operator response times indicated for this time study are the governing case with respect to operator actions during safe and alternate shutdown.

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4. NRC Request Provide an updated draft of BVPS OM Chapter 56C, " Alternate Safe Shutdown From Outside Control Room".

Response

DLC provided an updated draft of BVPS _0M-56C, Issue 1/ Revision 1, via express mail on April 27, 1987. - The latest approved version of OM-56C, Issue 1/ Revision 1, was provided via express mail on May 1, 1987.

5. NRC Request Indicate the number of plant personnel needed for alternate shutdown and whether this number includes Fire Brigade members.

Response

Five individuals are utilized for alternate shutdown as described in OM-56C, Section 1, Pages 3 and 4. However, as identified on Page 3, the Administrative Assistant is responsible for making the necessary EPP and plant personnel notifications. Thus, only four operators are utilized for performing tasks to assure safe shutdown. These individuals will not detract from the required number (5) of Fire Brigade members to be onsite at all times.

6. NRC Request List repairs required prior to initiation of the RHR system for each fire area. Also address materials available for the repairs.

Response

Section 3 of the Fire Protection Safe Shutdown Report (FPSSR), " Fire Area Review", lists the repairs required for each fire area (see Section 3.X.5). All repairs identified can be done with materials and tools read-ily available onsite. No replacement of components or routing of addi-tional cables is required.

7. NRC Request List actions required for the high-low pressure interfaces during alter-nate shutdown including actions for the pressurizer PORVs not controlled from the alternate shutdown panel, the reactor vessel head vent valves, and any other valves at a high-low pressure interface. The operating procedures should state that these valves will be de-energized during alternate shutdown.

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Response

~The required actions for the high-low pressure interface during alternate shutdown are stated for each fire area in the FPSSR.

"High-low pressure interfaces" are considered valves forming a boundary of the reactor coolant system.~ These interfaces consisted of the RHR ' System supply isolation valves, the pressurizer PORVs and block valves, the reac--

tor vessel head vents, . the drain isolation valves, and the letdown and .

excess. letdown. lines.

0M-56C, Section 4.C, Page C10 of 13, . Actions 7 and ' 9, indicate that the pressurizer PORVs not controlled from the alternate shutdown panel and the reactor vessel head vent valves are de-energized during alternate ' shut-down. The letdown and excess letdown . lines, the RHR supply isolation .

valves, and the drain isolation valves will be addressed as- described in BVPS OM Chapter 56B, " Fire Prevention and Control" (See NRC Request No.

12). All actions identified within the FPSSR have been verified to be included in _the appropriate operating procedurec..

8. .NRC Request FPSSR Section 3.11, " Fire Area CV Cable Vault. and Rod Control Area",

. Page 3.11-10, states that PORV block valve 2RCS*MOV535 must be repaired.

' Explain why this valve must be. repaired.

Response

In Fire Area CV-1, RCS depressurization is achieved utilizing Path B which encompasses 2RCS*PCV455C and 2RCS*M0V535. Ct. oles associated with 2RCS*MOV 535 are routed through this area. The analysis identified the potential for this valve to be driven shut. The repair. identified on Page 3.11-10 of the FPSSR will ensure that this valve will be open as required.

9. NRC Request Indicate whether the repairs listed in FPSSR Section 3.12, " Fire Area CV-2

- Cable Vault and Rod Control Area", are for hot or cold shutdown.

Response

These repairs are for cold shutdown.

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• 10. . NRC R* quest Indicate the locations _ where temporary ventilation is required following a

-fire. . Indicate which fire areas, when subjected to a fire, result in the need - for -temporary ventilation. Indicate what means are available to provide temporary ventilation.

Response

. The Emergency Exhaust Ventilation System provided for the Auxiliary Build-ing supplies ' cooling to the charging pump cubicles, component cooling water pump area,- and Post-Accident Sampling System (PASS) room upon loss

. of normal ventilation. As the PASS room is not required to be manned during a fire, and the component cooling water pump area is in an open area, ventilation is not required to be supplied to these areas after a fire. _ The charging-pumps are enclosed in individual cubicles with only a labyrinth-type opening. Heat-up calculations indicate that portable ventilation must be initiated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to meet equipment qualifi-cation requirements.

Temporary ventilation for the charging pump cubicles is needed following a fire' in the following fire areas:

CB-1 (Instrumentation and Relay Room, Elev. 707'-6")

CB-2 (Cable Spreading Room, Elev. 725'-6)

CB-3(ControlRoom,Elev.735'-6")

CB-6 (West Communication-Room - ESP Station, Elev. 707'-6")

CT-1 (Cable Tunnel / Fan Room, Elev.- 712'-6"/773'6")

CV-3 (Cable Vault and Rod Control, Elev. 755'-6")

PA-3 (Auxiliary Building, Elev. 710'-6" through 755'-6")

PA-4 ( Auxiliary Building, Elev. 755'-6")

SB-3 (Service Building - Cable Tray Area, Elev. 745'-6")

Temporary ventilation is provided through the use of five portable exhaust blowers with a capacity of 5000 cfm each. These units are designated for Fire Brigade use only. Three of the units are gasoline driven and two are electric. The Fire Brigade has a gasoline driven generator available.

, 11. NRC Reque_st FPSSR Section 3.3, " Fire Area CB Control Building Instrumentation and Relay Area", Pages 3.3-11 and 12, indicate that SWS valves are to be repaired. Explain why these valves need to be repaired.

Response

Valves 2SWS*M0V153-2 and 2SWS*MOV154-2, shown on FPSSR Figure 2.5-2, provide cooling water to the Reactor Containment air recirculation cooling coils. These units provide air to the RHR area of containment.

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12. NRC Request Provide an t.pdated copy of BVPS OM Chapter 568, " Fire Prevention and Control".

i-I . Response DLC provided the latest approved version of BVPS OM-56B, Issue 1/ Revision i

1, via express mail on May 1,1987.

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13. NRC Request Indicate the number of transfer switches provided for alternate shutdown

.and the location of these transfer switches. Also, indicate what power they transfer.

Response

There are _38 ' transfer switches provided for alternate shutdown. The transfer switches are located in the Alternate Shutdown Panel (ASP) room and are provided for the transfer of control power to the instruments provided on the ASP.

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