ML20212J839

Forwards RAI Re Request for Amends to Ts.Addl Info Needed to Complete Review to Verify That Proposed TS Are Consistent with & Validate Design Basis Analysis.Request Discussed with H Mahan on 990930.Info Needed within 10 Days of This Ltr

ML20212J839
Person / Time
Site:	Farley
Issue date:	09/30/1999
From:	Padovan L NRC (Affiliation Not Assigned)
To:	Dennis Morey SOUTHERN NUCLEAR OPERATING CO.
References
TAC-MA4943, TAC-MA4944, NUDOCS 9910060008
Download: ML20212J839 (5)

Text

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• Mr. D. N. Morey September 30, 1999 Vice Pr:sident - F:riey Project  !

South:rn Nuclear Operating Company, Inc.

Post Office Box 1295 -

Birmingham, Alabama 35201-1295 I i

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 RE: REQUEST FOR I ADDITIONAL INFORMATION - FILTRATION SYSTEM AND RADIATION MONITORING INSTRUMENTATION TECHNICAL SPECIFICATIONS CHANGE REQUEST (TAC NOS. MA4943 AND MA4944)

Dear Mr. Morey:

Your letter dated June 30,1997, supplemented by letters dated February 22, March 19, and June 30,1999, requested amendments to the Farley Nuclear Plant (FNP), Units 1 and 2, Technical Specifications (TS). ' You proposed revising the TS to clarify surveillance ,

requirements for the control room emergency filtration system, penetration room filtration  !

I system, fuel storage pool ventilation, and radiation monitoring instrumentation. You also l proposed to delete the containment purge exhaust filter.

We need the additional information requested in the Enclosure in order to complete our review ,

of your request. We will use the additional information to verify that your proposed TS are consistent with and validate your design basis analysis in these areas. Please send us this ]

information within 10 days of the date of this letter. I discussed this request with Howard i Mahan on September 30,1999, and we mutually agreed to this response date. Please call me at (301) 415-1423 if you need to revise the date.  :

Sincerely,-  :

ORIGINAL SIGNED BY:

L. Mark Padovan, Project Manager, Section 1 ,

Project Directorate ll Division of Licensing Project Management Office of Nuclear Reactor Regulation i Docket Nos. 50-348 and 50-364

Enclosure:

Request for AdditionalInformation cc w/ encl: See next page y

DISTRIBUTION:

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• Docket File- SBlack PSkinner, Ril JHayes PUBLIC ACRS HBerkow i PDil 1 R/F OGC HWalker DOCUMENT NAME: G:\PDii-1\Farley\MA4943&4RAlrev1.wpd '

To receive a copy of this document, indicate in the box: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy OFFICE PDil-1/PM -E PDil-1/LA b PDll-1/SC l NAME MPadovaI CHawes b REmch -

DATE 3M / /99 9 /M/99 Y/ M99

, OFFICIAL RECORD COPY j l 9910060008 990930

. PDR ADOCK 05000348 P PDR J

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g- t UNITED STATES j NUCLEAR REGULATORY COMMISSION

• WASHINGTON, D.C. 206f60001 September 30,.1999

% ..... /

Mr. D. N. Morey Vice President - Farley Project '

Southern Nuclear Operating Company, Inc.

Post Office Box 1295 Birmingham, Alabama 35201-1295

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 RE: REQUEST FOR J

ADDITIONAL INFORMATION - FILTRATION SYSTEM AND RADIATION l MONITORING INSTRUMENTATION TECHNICAL SPECIFICATIONS CHANGE I REQUEST (TAC NOS. MA4943 AND MA4944) I

Dear Mr. Morey:

Your letter dated June 30,1997, supplemented by letters dated February 22, March 19, and June 30,1999, requested amendments to the Farley Nuclear Plant (FNP), Units 1 and 2, Technical Specifications (TS). You proposed revising the TS to clarify surveillance I requirements for the control room emergency filtration system, penetration room filtration system, fuel storage pool ventilation, and radiation monitoring instrumentation. You also proposed to delete the containment purge exhaust filter.

We raed the additional information requested in the Enclosure in order to complete our review of your request. We will use the additional information to verify that your proposed TS are consistent with and validate your design basis analysis in these areas. Please send us this ,

information within 10 days of the date of this letter. I discussed this request with Howard i Mahan on September 30,1999, and we mutually agreed to this response date. Please call me i at (301) 415-1423 If you need to revise the date.

Sincerely,

& 6bn L. Mark Padovan,. Project Manager, Section 1 Project Directorate 11 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364

Enclosure:

Regiest for Additional Information cc w/ encl: See next page j

m

,j ..-

i Joseph M. Farley Nuclear Plant cc:

Mr. L. M. Stinson Rebecca V. Badham GeneralManager _

SAER Supervisor Southern Nuclear Operating Company Southern Nuclear Operating Company

~ Post Office Box 470 P. O. Box 470 Ashford, Alabama 36312 Ashford, Alabama 36312 )

Mr. Mark Ajiuni, Licensing Manager.

1 Southern Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201-1295 Mr. M. Stanford Blanton Balch and Bingham Law Firm i Post Office Box 306 1710 Sixth Avenue North Birmingham, Alabama 35201

. Mr. J. D. Woodard Executive Vice President Southern Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201 State Health Officer Alabama Department of Public Health 434 Monroe Street Montgomery, Alabama 36130-1701 Chairman Houston County Commission Post Office Box 6406 Dothan, Alabama 36302 i

Resident inspector.

U.S. Nuclear Regulatory Commission i 7388 N. State Highway 95 - 4 Columbia, Alabama 36319  !

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s REQUEST FOR ADDITIONAL INFORMATION FILTRATION SYSTEM. FUEL STORAGE POOL VENTILATION. AND RADIATION MONITORING INSTRUMENTATION TECHNICAL SPECIFICATIONS CHANGE REQUEST JOSEPH M. FARLEY NUCLEAR PLANT. UNITS 1 AND 2

1. The penetration room filtration (PRF) system is designed to filter 1) ECCS leakage in the event of a loss of-coolant accident (LOCA) and 2) the release of radioactivity in the event of a fuel handling accident in the spent fuel pool area. The PRF system design basis is that it will process all of the radioactivity released from these accidents. You proposed technical specifications (TS) changes to demonstrate a negative 1/8 inch w.g. pressure relative to adjacent areas for the LOCA system alignment. However, you did not propose TS for the fuel handling system alignment. Please propose a TS surveillance for the fuel handling system alignment at 5000 cfm +/-10% flow. Also, please propose performing your PRF TS surveillance at +/-10% flow.

2. Do you also perform Improved Standard Technical Specifications (ISTS) Surveillance 3.7.12.1 during spent fuel storage on a 7-day basis or does another technical specification address the PRF with spent fuel storage?

3. You proposed changes to the control room emergency filtration system (CREFS)

Surveillance Requirement (SR) 4.7.7.1.a and its Bases to indicate that the heater circuits were energized during the 10-hour test. Please reword.the SR and its Bases to match the ISTS wording for heaters being on and/or energized and clarify the Bases to discuss your heater controls during the 10-hour test.

4. For accident mitigation, does the CREFS initiate on a Hi-Rad signal and a safety injection signal?

5. Ghould Action 27 of Table 3.3-6 indicate emergency pressurization and recirculation flow?

The control room emergency ventilation system TS clearly differentiate between recirculation and pressurization.

6. What is the setpoint for the containment purge radiation monitor and what source term was used (Ci/MWT)?

7. The following concern removing the containment purge system (affecting fuel handling accident inside containment):

a. What is the surface area of the pool?

b. What is the distsnce from the pool surface to the point where the air from the pool surface would enter the purge header?

Enclosure l-

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c. At what activity level (uCi/ unit volume, e.g., cubic feet) would S.NC isolate the containment purge?J

~ d. Have you determined that with a dilution of one third of the containment (660,000 ft )

that the. rad monitor would cause an isolation?

e. SNC's analysis for removing the containment purge filter ventilation system assumed mixing in the containment associated with the containment purge system. Although the filtration system is being removed, will the remaining portions of the system remain safety related with ties to the' emergency diesels, and will they remain in the TSs?

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