ML020270014

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Request for Additional Information, Change to Technical Specification 3/4.7.B.1.a.2, Standby Gas Treatment Heater Requirement.
ML020270014
Person / Time
Site: Pilgrim
Issue date: 02/01/2002
From: Starkey R
NRC/NRR/DLPM/LPD1
To: Clifford J
NRC/NRR/DLPM/LPD1
Starkey, D, NRR/DLPM, 415-1122
References
TAC MB2775
Download: ML020270014 (4)


Text

February 1, 2002 MEMORANDUM TO: James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Robert D. Starkey, Project Manager, Section 2 /RA/

Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION (RAI), PILGRIM NUCLEAR POWER STATION, CONCERNING CHANGE TO TECHNICAL SPECIFICATION 3/4.7.B.1.a.2, STANDBY GAS TREATMENT HEATER REQUIREMENT (TAC NO. MB2775)

The attached RAI was transmitted by e-mail on January 23, 2002, to Mr. Bryan Ford of Entergy Nuclear Generation Company (ENGC) (the licensee). The RAI was transmitted to facilitate the technical review being conducted by NRR. Subsequent to the e-mail transmission, the RAI was discussed with the licensee during a phone call on January 25, 2002, during which the licensee agreed to respond in writing to the RAI. In the submittal, the licensee requested to test the Standby Gas Treatment System heaters to a higher output, at least 20 kW, based upon revised design basis calculations. This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensees request.

Docket No. 50-293

Attachment:

Request for Additional Information, Pilgrim Nuclear Power Station, Proposed License Amendment Change to the Technical Specification 3/4.7.B.1.a.2, Standby Gas Treatment (SBGT) Heater Requirement

February 1, 2002 MEMORANDUM TO: James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Robert D. Starkey, Project Manager, Section 2 /RA/

Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION (RAI), PILGRIM NUCLEAR POWER STATION, CONCERNING CHANGE TO TECHNICAL SPECIFICATION 3/4.7.B.1.a.2, STANDBY GAS TREATMENT HEATER REQUIREMENT (TAC NO. MB2775)

The attached RAI was transmitted by e-mail on January 23, 2002, to Mr. Bryan Ford of Entergy Nuclear Generation Company (ENGC) (the licensee). The RAI was transmitted to facilitate the technical review being conducted by NRR. Subsequent to the e-mail transmission, the RAI was discussed with the licensee during a phone call on January 25, 2002, during which the licensee agreed to respond in writing to the RAI. In the submittal, the licensee requested to test the Standby Gas Treatment System heaters to a higher output, at least 20 kW, based upon revised design basis calculations. This memorandum and the attachment do not convey or represent an NRC staff position regarding the licensees request.

Docket No. 50-293

Attachment:

Request for Additional Information, Pilgrim Nuclear Power Station, Proposed License Amendment Change to the Technical Specification 3/4.7.B.1.a.2, Standby Gas Treatment (SBGT) Heater Requirement DISTRIBUTION PUBLIC J. Clifford D. Starkey D. Nguyen PDI-2 Reading Accession No. ML020270014 OFFICE PDI-2/PM PD1-2/SC NAME DStarkey:as JClifford DATE 1/28/02 OFFICIAL RECORD COPY

REQUEST FOR ADDITIONAL INFORMATION PILGRIM NUCLEAR POWER STATION PROPOSED LICENSE AMENDMENT CHANGE TO THE TECHNICAL SPECIFICATIONS 3/4.7.B.1.a.2 STANDBY GAS TREATMENT (SBGT) HEATER REQUIREMENT The first paragraph on page 4 of ATTACHMENT A, of the August 22, 2001, submittal states that the effects (e.g., increased electrical load and heat load on components and charcoal) of the larger heaters have been evaluated and found not to adversely impact other equipment.

With regard to that statement, please provide a detailed discussion as to why the increased electrical load of the larger heaters will not adversely impact other equipment during a design basis accident. In your response, please consider the increased loading on supply breakers, cable sizing, motor control center loading and diesel generator loading. Please provide sufficient data to support the conclusion.

Attachment