ML072700754

Draft RAI on Alternate Source Term Amendment

ML072700754
Person / Time
Site:	Palisades
Issue date:	12/05/2006
From:	Padovan L Office of Nuclear Reactor Regulation
To:	Hazelhoff A - No Known Affiliation
References
TAC MD3087
Download: ML072700754 (3)

Text

Hazelhoff, Amy C.

From: L Mark Padv]

ent: TuesdayQecember 05, 2006 2*2 PM 1,0: Hazelho C.

Subject:

Draft AST RAI Attachments: Palisades - Alternate Source Term RAI.pdf Palisades -

Nlternate Source T..

Amy, See attached draft RAI. Is it clear? Need a call? When can you reply?

Mark

Mr. Paul A. Harden Site Vice President Nuclear Management Company, LLC Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530

SUBJECT:

PALISADES NUCLEAR PLANT - REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT RELATED TO APPLICATION OF ALTERNATE SOURCE TERM (TAC NO. MD3087)

Dear Mr. Harden:

Nuclear Management Company, LLC's (NMC's) letter of September 25, 2006, submitted a license amendment to incorporate changes into the Technical Specifications for Palisades Nuclear Plant that will implement the alternate source term as described in Regulatory Guide 1.183. We are reviewing your request, and find that additional information is needed as shown in the enclosed request for additional information (RAI).

I discussed the enclosed RAI with Ms. Amy Hazelhoff of your organization on 2006, and she agreed to respond within days of receipt of this RAI. Please contact me at (301) 415-1423 ifyou have questions.

Sincerely, L. Mark Padovan, Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation D:;E6cet- No. 50-255

Enclosure:

RAI

.. c.Q.w/encl: See next page

REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST RELATED TO ALTERNATE SOURCE TERM PALISADES NUCLEAR PLANT NUCLEAR MANAGEMENT COMPANY, LLC DOCKET NUMBER 50-255

1. On Section 2.1.2 of your application you stated that the sump pH is controlled at a value greater than 7 based on the addition of tri-sodium phosphate (TSP) baskets or an alternate buffer. Clarify what type of alternate buffer could be used to control containment sump pH.

2. In order to complete its evaluation, the NRC staff needs to review the general assumptions and calculations used to prove that the containment sump pH will be maintained above 7 for 30 days following a Loss-of-Coolant Accident (LOCA). Provide this information in sufficient detail for the NRC staff to perform independent calculations to evaluate the licensee's conclusion (if different buffers could be used, provide the information requested for each buffer). If the calculations were performed manually, describe the methodology and provide sample calculations. If a computer code was used, describe the code and provide the input values and how they were determined.

Provide the results of pH calculations at different time intervals and explain how the time intervals were selected.

3. The discussion of backleakage to the safety injection refueling water tank (SIRWT) in Section 2.1.3 of the application provides the maximum pH, maximum iodine concentration and maximum elemental iodine fraction of the SIRWT at 30 days. Provide the general assumptions and calculations used to determine the maximum pH, maximum iodine concentration and maximum elemental iodine fraction of the SIRWT at 30 days. Provide this information in sufficient detail for the NRC staff to perform independent calculations to evaluate the licensee's conclusion. If the calculations were performed manually, describe the methodology and provide sample calculations. If a computer code was used, describe the code and provide the input values and how they were determined.

ENCLOSURE