ML20050B184

Forwards Addl Info Requested by Auxiliary Sys & Instrumentation Sys Branches to Complete Fire Protection Reviews.Remaining Issue Re Loss of non-Class IE Buses Will Be Included in Emergency Procedures

ML20050B184
Person / Time
Site:	Waterford
Issue date:	03/30/1982
From:	Maurin L LOUISIANA POWER & LIGHT CO.
To:	Tedesco R Office of Nuclear Reactor Regulation
References
IEB-79-27, W3P82-0629, W3P82-629, NUDOCS 8204050078
Download: ML20050B184 (5)

Text

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LOUISIANA 142 OR ARONDE STRUT P O W E R & L i G H T! P O BOX 600H* NEW ORLEANS LOUISlANA 70174 = (504) 366 2345

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L.V. MAURIN l Vice President Nuclear Operations March 30, 1982 t-

1. hiQ4 W3P82-0629 3-A20.12 O Q-3-P43 4)

SGCc Mr. Robert L. Tedesco g7 D -

Assistant Director of Licensing Ng /g f U. S. Nuclear Regulatory Commission ;M V ^

Washington, DC 20555 p

SUBJECT:

Waterford SES Unit No. 3 <u e N

Docket No. 50-382 Responses to Supplementary Questions

REFERENCES:

(1) LP&L letter (L. V. Maurin to R. L. Tedesco) W3P81-2568, dated November 16, 1981.

(2) LP&L Ictter (L. V. Maurin to R. L. Tedesco) W3P81-2813, dated December 21, 1981.

(3) LP&L letter (L. V. Maurin to D. G. Eisenhut) W3P81-2344, dated November 10, 1981.

(4) NRC letter (D. G. Eisenhut to L. V. Maurin), dated September 30, 1981.

ATTACHMENTS: (1) Auxiliary Systems Branch Questions on " Response to NRC Supplemental Questions" (Appendix 9.5A).

(2) ICSB Questions on " Response to NRC Supplemental Questions" (Appendix 9.5A).

Dear Mr. Tedesco:

On October 9, 1981, during a telephone conversation among the NRC staff, LP&L, and Ebasco Services, Inc., thirty-two (32) open items were identified as a re-sult of the Staff's fire protection review of Waterford-3. One of these open items required installation of th or 3-hour rated fire dampers or doors in cer-tain specified ventilation penetrations. In reference (1), LP&L addressed this concern and committed to the installation of appropriate fire dampers. Refer-ence (1) was then incorporated into the FSAR as Appendix 9.5B in December, 1981.

8204050078 820330 PDR ADOCK 05000 SlI I

"W3P82-0629

. Mr. Robert L. Tedesco

• Page 2 In reference (2), LP&L provided a response to the five part CMEB FSAR Question 040.148. Reference (2) also contained a tabulation or the remaining open items from the October 9, 1981, telecon and our proposed resolution. Reference (2) will be incorporated into the FSAR as Appendix 9.5A in Amendment 26, currently scheduled for docketing in April, 1982. References (1) and (2) supplement or revise some portions of previous information given in FSAR Section 9.5.1. This section will be updated in Amendment 26 to be consistent with references (1) and (2). References (4) and (3) were a request for the status of LP6L compliance with 10CFR50 Appendix R, and our response, respectively.

Since submission of references (1) and (2) to the NRC, the Auxiliary Systems and Instrumentation Systems Branches have informally conveyed a number of requests for information needed to complete their fire protection reviews. Accordingly, and at their request, we submit this information as Attachments 1 and 2 in a question and answer format. This information shall be formally incorporated into the FSAR in the next Amendment.

The fire protection open items identified in SER Section 1.7 relating to FSAR Chapters 7, 8 and 9, have been addressed for the most part by this submittal in conjunction with References (1), (2), and (3). The sole remaining issue deals with procedures required to address loss of non-Class IE buses, outlined in IE Bulletin 79-27. Provisions to deal with this event will be included in the Waterford Emergency Procedures, currently scheduled for completion prior to fuel load. Therefore, we believe that the information contained in this submittal satisfies your staff's concerns regarding the adequacy of our fire protection design.

Thank you for your cooperation.

Yours very truly,

/

1 L. V. Maurin w

LVM/RMF/1gh Attachments cc: E. L. Blake 1 W. M. Stevenson S. Black (NRC-LPM)

J. Wermeihl (AS3)

R. Stevens (ICSB)

Attachment (1)

AUXILIARY SYSTEMS BRANCH QUESTIONS ON LP&L FIRE PROTECTION SUBMITTAL Q.1 TABLE 9.5A-lb page 2. Neutron flux is shown as "later". Is this the startup channel? Is it on LCP-43? Is it routed independently from the control room? -

R.1 This is the startup channel. Indication is provided on both LCP-43 and in the control room. Cable protection to meet Appendix R criteria will be provided commensurate with the protection provided for other essential cables. Cabic routing details will be provided in the formal FSAR Amendment.

Q.2 TABLE 9.5A-lb page 15. Is the Steam Generator Wide Range-Level Trans-mitter on LCP-43? Is it routed independently from the control room?

R.2 The Steam Generator Wide Range Level Transmitter indication is provided on LCP-43 and in the control room. Cable protection to meet Appendix R criteria will be provided commensurate with the protection provided for other essential cables.

Q.3 TABLE 9.5-2b page 5. Why isn't RCS Hot Leg Temperature indicated on this table?

R.3 Both RCS Hot Leg and Cold Leg Temperature indication is now provided on LCP-43 and in the control room. The cable routings to LCP-43 and to the control room are completely separate and independent. This information shall be included in t his table in the next FSAR amendment.

Q.4 Provide justification or reference responses to other NRC Branch questions to demonstrate that cold shutdown can be achieved without the letdown line in operation. In particular, are all valves required for this path depicted on Table 9.5A-2b?

R.4 Cold shutdown can be achieved without letdown. Please refer to responses to NRC Reactor Systems Branch Questions 211.3, 211.14.lb, 211.17 and 211.94(4).

Cold shutdown without letdown can be achieved by realigning the suction of the charging pumps to the Boric Acid Make-up Tanks via the gravity flow lines, and using the Pressurizer Auxiliary Spray lines. This can all be accomplished from either the control room or LCP-43. Cable protection to meet Appendix R criteria will be provided commensurate with the protection provided for other essential cables.

t Attachment (1)

, 1 Valve manipulations' required are as follows:

Valve Description *

. Tag No. Action 0 Gravity feed,5 rom BAMT 3CH-V106A Open ,

O Gravity feed fr'om BAMT 3CH-V107B Open VCT Discharge 2CH-V123A/B Close

\i o Aux Spray Valve ICH-E2505A Open 0AuxSpray' halve l' ICH-E2505B Open Charging Line to Loop 2A

• j '2CH-E2504B Close Charging Line to Loop 1A ,

, ICH-E2503A 'Close 1 ,

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• Thesc ; valves are included in' Table! 9.5AL2b in' Reference 2. The other valves will be includdd in this table.inithe next FSAR amendment. Cable routing protection to' meet Appendix R c'riteria will be provided commensurate.with the protection'provided other essential cables.

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Attachment (2)

ICSB QUESTIONS ON LP&L FIRE PROTECTION SUBMITTAL Q.1 TABLE 9.5A-la page 15. Are there control switches for the ADV's ac LCP-43?

Is the designation for these valves on FSAR Table 7.4-3 correct?

R.1 There are control switches for the ADV's on LCP-43 and the designation in FSAR Table 7.4-3 is correct.

Q.2 TABLE 9.5A-la page 25. What is the correspondence between the components listed as PZR Her Banks 3A-SA and 3d-SB on Tabic 9.5A-la and the components designated Proporticaal Heater Banks 1 and 2 on FSAR Table 7.4-37 R.2 Proportional Heater Bank 1 is PZR Her Bank 3A-SA; Proportional Htr Bank 2 is RZR Htr Bank 3B-SB.

Q.3 TABLE 9.5a-2b page 2. Are both Aux Spray Valves on LCP-437 If so FSAR Table 7.4-3 should be revised.

R.3 Both Aux Spray Valves are on LCP-43; Table' 7.4-3 will be revised to reflect this.

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