ML110090027

Request for Additional Information Revision to TS for Setpoint and Setpoint Tolerance Increase for Safety Relief Valves and Spring Safety Valves, and Related Changes (ME3543)

ML110090027
Person / Time
Site:	Pilgrim
Issue date:	01/10/2011
From:	Richard Guzman Plant Licensing Branch 1
To:	Entergy Nuclear Operations
Guzman R, NRR/DORL, 415-1030
References
TAC ME3543
Download: ML110090027 (4)

Text

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Site Vice President Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - PILGRIM NUCLEAR POWER STATION - TO SUPPORT THE REVIEW OF SETPOINT AND SETPOINT TOLERANCE INCREASES FOR SAFETY RELIEF VALVES AND SPRING SAFETY VALVES (TAC NO. ME3543)

Dear Sir or Madam:

By letter dated March 15, 2010 (Agencywide Documents Access Management System (ADAMS) Accession No. ML100770450), Entergy Nuclear Operations, Inc. (Entergy), the licensee for Pilgrim Nuclear Power Station, submitted a license amendment request (LAR) to revise its Technical Specifications to modify the setpoint and setpoint tolerances for Safety Relief Valves (SRVs) and Spring Safety Valves (SSVs) and changes related to the replacement of (i) four (4) Target Rock Two-Stage SRVs with Three-Stage SRVs, and (ii) two existing Dresser 3.749 inch-throat diameter SSVs with Dresser 4.956 inch-throat diameter SSVs.

On June 3, 2010, the Nuclear Regulatory Commission (NRC) staff issued a request for additional information (RAI) concerning the LAR. The RAI included two requests (RAI-1 and RAI-2) related to the Setpoint Methodology for the proposed Anticipated Transient Without Scram/High Pressure Recirculation Pump Trip trip setpoint. By letter dated August 30, 2010 (ADAMS Accession No. ML102510137), Entergy provided responses to the staff's RAls. The NRC staff has reviewed Entergy's response in that letter, and has determined that the supplemental information did not completely address the staffs June 3, 2010, RAls. Enclosed is the NRC staff's supplemental RAls which provide the additional information needed by the staff to complete this review.

The informational needs were discussed with your staff on January 6, 2011, and it was agreed that your response would be provided by January 31, 2011.

Sincerely, Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293

Enclosure:

As stated cc w/encl: Distribution via Listserv

SUPPLEMENTAL REQUEST FOR ADDITIONAL INFORMATION (RAI)

ENTERGY NUCLEAR OPERATIONS, INC.

PILGRIM NUCLEAR POWER STATION REVIEW OF SETPOINT AND SETPOINT TOLERANCE INCREASES FOR SAFETY RELIEF VALVES AND SPRING SAFETY VALVES DOCKET NO. 50-293 The Nuclear Regulatory Commission (NRC) staff is reviewing the Entergy Nuclear Operations, Inc. (Entergy or the licensee) submittal dated March 15,2010. By letter dated August 30, 2010, Entergy provided responses to the staff's RAls. The NRC staff has reviewed that letter, and has determined that the supplemental information did not completely address the staff's concerns.

In order for the NRC staff to complete its review; the clarifying information items described below will need to be addressed.

1. Definition of "Trip Level Setting" in TS Table 3.2-G:

Clarify what the column title, "Trip Level Setting," in TS Table 3.2-G, "Instrumentation That Initiate Recirculation Pump Trip and Alternate Rod Insertion," represents compared to the setpoint terms listed in Figure 1 of Regulatory Guide (RG) 1.105, "Setpoints for Safety-Related Instrumentation," Revision 3, dated December 3, 1999.

2. Setpoint Calculation Methodology:

Provide documentation of the methodology used for establishing the limiting trip setpoint or normal trip setpoint and limiting acceptable values for the as-found and as-left setpoints as measured during the periodic surveillance testing. Documentation should:

• Include calculations.

• Indicate Analytical Limits and/or other limiting design values.

• Indicate the source of the parameters (tolerances) used in calculating these three setpoint values and how they comply with RG 1.105 to ensure the 95/95 confidence level is achieved and that these setpoints are adequate for the surveillance test interval specified in the plant surveillance requirements.

• As applicable, provide reference(s) to NRC approved documents related to this setpoint calculation.

Enclosure

-2

3. Test Procedures:

Describe the measures to be taken to ensure that the associated instrument channels are capable of performing specified functions in accordance with applicable design requirements and associated analysis, including:

• Information on the controls employed to ensure that the as left trip setting after completion of periodic surveillance is consistent with the setpoint methodology.

• Discussion on the plant corrective action process for restoring the channels to operable status.

January 10, 2011 Site Vice President Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - PILGRIM NUCLEAR POWER STATION - TO SUPPORT THE REVIEW OF SETPOINT AND SETPOINT TOLERANCE INCREASES FOR SAFETY RELIEF VALVES AND SPRING SAFETY VALVES (TAC NO. ME3543)

Dear Sir or Madam:

By letter dated March 15,2010 (Agencywide Documents Access Management System (ADAMS) Accession No. ML100770450), Entergy Nuclear Operations, Inc. (Entergy), the licensee for Pilgrim Nuclear Power Station, submitted a license amendment request (LAR) to revise its Technical Specifications to modify the setpoint and setpoint tolerances for Safety Relief Valves (SRVs) and Spring Safety Valves (SSVs) and changes related to the replacement of (i) four (4) Target Rock Two-Stage SRVs with Three-Stage SRVs, and (ii) two existing Dresser 3.749 inch-throat diameter SSVs with Dresser 4.956 inch-throat diameter SSVs.

On June 3, 2010, the Nuclear Regulatory Commission (NRC) staff issued a request for additional information (RAI) concerning the LAR. The RAI included two requests (RAI-1 and RAI-2) related to the Setpoint Methodology for the proposed Anticipated Transient Without Scram/High Pressure Recirculation Pump Trip trip setpoint. By letter dated August 30, 2010 (ADAMS Accession No. ML102510137), Entergy provided responses to the staff's RAls. The NRC staff has reviewed Entergy's response in that letter, and has determined that the supplemental information did not completely address the staff's June 3, 2010, RAls. Enclosed is the NRC staff's supplemental RAls which provide the additional information needed by the staff to complete this review.

The informational needs were discussed with your staff on January 6, 2011, and it was agreed that your response would be provided by January 31, 2011.

Sincerely, IRA!

Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293

Enclosure:

As stated cc w/encl: Distribution via Listserv DISTRIBUTION:

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