ML090860966

Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendments Deletion of Technical Specification Requirements Related to Plant Staff Working Hours (TAC Nos. MD9309, MD9310 and MD9311)

ML090860966
Person / Time
Site:	Salem, Hope Creek
Issue date:	05/14/2009
From:	Richard Ennis Plant Licensing Branch 1
To:	Joyce T Public Service Enterprise Group
Ennis R B, NRR/DORL, 415-1420
References
TAC MD9309, TAC MD9310, TAC MD9311
Download: ML090860966 (20)

Text

UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 May 14, 2009 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear P.O. Box 236, N09 Hancocks Bridge, NJ 08038 HOPE CREEK GENERATING STATION AND SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 -ISSUANCE OF AMENDMENTS RE: DELETION OF TECHNICAL SPECIFICATION REQUIREMENTS RELATED TO PLANT STAFF WORKING HOURS (TAC NOS. MD9309, MD9310 AND MD9311)

Dear Mr. Joyce:

The Commission has issued the enclosed Amendment No. 177 to Facility Operating License (FOL) No. NPF-57 for the Hope Creek Generating Station (Hope Creek) and Amendment Nos. 290 and 274 to FOL Nos. DPR-70 and DPR-75 for the Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2. The amendments delete the requirements related to plant staff working hours from Section 6.0, "Administrative Controls" of the respective plants' Technical Specifications (TSs) in response to your application dated July 21, 2008. The requirements being deleted had been incorporated into the TSs based on the guidance in Generic Letter (GL) 82-12, "Nuclear Power Plant Staff Working Hours." The guidance in GL 82-12 has been superseded by the requirements in Title 10 of the Code of Federal Regulations (10 CFR), Part 26, "Fitness for Duty Programs," Subpart I, "Managing Fatigue." A copy of our safety evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice. Sincerely, Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-354, 50-272 and 50-311

Enclosures:

1. Amendment No. 177 to License No. I\IPF-57

2. Amendment No. 290 to License No. DPR-70

3. Amendment No. 274 to License No. DPR-75

4. Safety Evaluation cc w/encls: Distribution via ListServ UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 PSEG NUCLEAR DOCKET NO. HOPE CREEK GENERATING AMENDMENT TO FACILITY OPERATING Amendment No. 177 License No. NPF-57 The Nuclear Regulatory Commission (the Commission) has found that: The application for amendment filed by PSEG Nuclear LLC dated July 21,2008, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-57 is hereby amended to read as follows:

-2Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 177, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into the license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. The license amendment is effective as of its date of issuance and shall be implemented by October 1, 2009. FOR THE NUCLEAR REGULATORY COMMISSION Harold K. Chernoff, Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the License and Technical Specifications Date of Issuance:

May 14, 2009 ATTACHMENT TO LICENSE AMENDMENT NO. 177 FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 Replace the following page of the Facility Operating License with the revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change. Remove Insert Page 3 Page 3 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Insert 6-2 6-2

-3PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and PSEG Nuclear LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is sUbject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: Maximum Power Level PSEG Nuclear LLC is authorized to operate the facility at reactor core power levels not in excess of 3840 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein. Technical Specifications and Environmental Protection Plan Technical Specifications contained in Appendix A, as revised through Amendment No. 177, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into the license. PSEG Nuclear LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. Inservice Testing of Pumps and Valves (Section 3.9.6, SSER No. 4)* This License Condition was satisfied as documented in the letter from W. R. Butler (NRC) to C. A. McNeill, Jr. (PSE&G) dated December 7, 1987. Accordingly, this condition has been deleted. parenthetical n otation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or supplements wherein the license condition is discussed.

Amendment No. 177 ADMINISTRATIVE CONTROLS UNIT STAFF (Continued)

b. At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor. In addition, while the unit is in OPERATIONAL CONDITION 1, 2 or 3, at least one licensed Senior Reactor Operator shall be in the control room; ALL CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or licensed Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

HOPE 6-2 Amendment No. 177 UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 PSEG NUCLEAR EXELON GENERATION COMPANY, DOCKET NO.

SALEM NUCLEAR GENERATING STATION, UNIT AMENDMENT TO FACILITY OPERATING Amendment No. 290 License No. DPR-70 The Nuclear Regulatory Commission (the Commission) has found that: The application for amendment filed by PSEG Nuclear LLC, acting on behalf of itself and Exelon Generation Company, LLC (the licensees) dated July 21,2008, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR), Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-70 is hereby amended to read as follows:

-2Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 290, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. This license amendment is effective as of its date of issuance and shall be implemented by October 1, 2009. FOR THE NUCLEAR REGULATORY COMMISSION -:

K. Chernoff, Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Facility Operating License and the Technical Specifications Date of Issuance:

May 14, 2009 ATTACHMENT TO LICENSE AMENDMENT NO. FACILITY OPERATING LICENSE NO. DOCKET NO. Replace the following page of Facility Operating License No. DPR-70 with the attached revised page as indicated. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Page 4 Page Replace the following page of the Appendix A, Technical Specifications, with the attached revised page as indicated. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove 6-2

-4Maximum Power Level PSEG Nuclear LLC is authorized to operate the facility at a steady state reactor core power level not in excess of 3459 megawatts (one hundred percent of rated core power) . Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 290, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. Deleted Per Amendment 22, 11-20-79 Less than Four Loop Operation PSEG Nuclear LLC shall not operate the reactor at power levels P-7 (as defined in Table 3.3-1 of Specification 3.3.1.1 of Appendix A to this license) with less than four (4) reactor coolant loops in operation until safety analyses for less than four loop operation have been submitted by the licensees and approval for less than four loop operation at power levels above P-7 has been granted by the Commission by Amendment of this license. PSEG Nuclear LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report, and as approved in the NRC Safety Evaluation Report dated November 20, 1979, and in its supplements, subject to the following provision:

PSEG Nuclear LLC may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of fire. Amendment No. 290 ADMINISTRATIVE CONTROLS FACILITY STAFF The facility organization shall be subject to the following: Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1; At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor. In addition, at least one licensed Senior Reactor Operator shall be in the Control Room area at all times. All CORE ALTERATIONS shall be observed and directly supervised by a licensed Senior Reactor Operator who has no other concurrent responsibilities during this operation.

SALEM -UNIT 6-2 Amendment No. 290 UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 PSEG NUCLEAR EXELON GENERATION COMPANY, DOCKET NO.

SALEM NUCLEAR GENERATING STATION, UNIT AMENDMENT TO FACILITY OPERATING Amendment No. 274 License No. DPR-75 The Nuclear Regulatory Commission (the Commission) has found that: The application for amendment filed by PSEG Nuclear LLC, acting on behalf of itself and Exelon Generation Company, LLC (the licensees) dated July 21,2008, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR), Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:

-2Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 274, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. This license amendment is effective as of its date of issuance and shall be implemented by October 1, 2009. FOR THE NUCLEAR REGULATORY COMMISSION Harold K. Chernoff, Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Facility Operating License and the Technical Specifications Date of Issuance:

May 14, 2009 ATTACHMENT TO LICENSE AMENDMENT NO. 274 FACILITY OPERATING LICENSE NO.

DPR-75 DOCKET NO. 50-311 Replace the following page of Facility Operating License No.

DPR-75 with the attached revised page as indicated. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Page 4 Page Replace the following page of the Appendix A, Technical Specifications, with the attached revised page as indicated. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Insert 6-2 6-2

-4 (2) Technical Specifications and Environmental Plan The Technical Specifications contained in Appendices A and S, as revised through Amendment No. 274, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Special Low Power Test Program PSE&G shall complete the training portion of the Special Low Power Test Program in accordance with PSE&G's letter dated September 5, 1980 and in accordance with the Commission's Safety Evaluation Report nSpecial Low Power Test Program n, dated August 22, 1980 (See Amendment No.2 to DPR-75 for the Salem Nuclear Generating Station, Unit No.2) prior to operating the facility at a power level above five percent. Within 31 days following completion of the power ascension testing program outlined in Chapter 13 of the Final Safety Analysis Report, PSE&G shall perform a boron mixing and cool down test using decay heat and Natural Circulation.

PSE&G shall submit the test procedure to the NRC for review and approval prior to performance of the test. The results of test shall be submitted to the NRC prior to starting up following the first refueling outage. (4) Initial Test Program PSE&G shall conduct the post-fuel-Ioading initial test program forth in Chapter 13 of the Final Safety Analysis Report, as amended) without making any major modifications of this program unless modifications have been identified and have received prior NRC approval.

Major modifications are defined as: Elimination of any test identified in Chapter 13 of the Final Safety Analysis Report, as amended, as essential; Modification of test objectives, methods or acceptance criteria for any test identified in Chapter 13 of the Final Safety Analysis Report, as amended, as essential; Performance of any test at a power level different by more than five percent of rated power from there described; and Amendment No. 274 ADMINISTRATIVE CONTROLS FACILITY STAFF (Continued) At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor. In addi tion, at least one licensed Senior Reactor Operator shall be in the Control Room area at all times. All CORE ALTERATIONS shall be observed and directly supervised by a licensed Senior Reactor Operator who has no other concurrent responsibilities during this operation. SALEM -UNIT 6-2 Amendment No. 274 UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 177,290 AND 274 TO FACILITY OPERATING LICENSE NOS. NPF-57, DPR-70 AND DPR-75 PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION AND SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-354, 50-272 AND 50-311

1.0 INTRODUCTION

By application dated July 21, 2008, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082140239), PSEG Nuclear LLC (PSEG or the licensee) submitted license amendment requests for the Hope Creek Generating Station (Hope Creek) and Salem Nuclear Generating Station (Salem) Unit Nos. 1 and 2. The proposed amendments would delete the requirements related to plant staff working hours from Section 6.0, "Administrative Controls" of the respective plants' Technical Specifications (TSs). The current working hour requirements were incorporated into the TSs as a result of the guidance in Nuclear Regulatory Commission (NRC or Commission)

Generic Letter (GL) 82-12, "Nuclear Power Plant Staff Working Hours." The guidance in GL 82-12 has been superseded by the requirements in Title 10 of the Code of Federal Regulations (10 CFR), Part 26, "Fitness for Duty Programs," Subpart I, "Managing Fatigue." The licensee stated that the proposed amendments would support implementation of the new requirements in Subpart I. 2.0 REGULATORY EVALUATIOI\l On February 8, 1982, the NRC staff issued GL 82-02, "Nuclear Power Plant Staff Working Hours" (ADAMS Legacy Library Accession No. 8202120001), which issued a policy statement on factors causing fatigue of operating personnel at nuclear reactors. GL 82-02 requested licensees to revise the administrative section of their TSs to require that administrative procedures follow the policy guidelines and that authorized deviations to the working hours guidelines be documented and available for NRC review. On June 15, 1982, the NRC staff issued GL 82-12 (ADAMS Legacy Library Accession No. 8206160341), which revised the guidance in GL 82-02. The guidance of GL 82-12 was incorporated into Section 6.0, "Administrative Controls" of the TSs for Hope Creek and Salem Unit Nos. 1 and 2.

Enclosure

-2On April 17, 2007, in the Staff Requirements Memorandum for SECY-06-0244 (ADAMS Accession No. ML071070361), the Commission approved a final rule amending 10 CFR Part 26, "Fitness for Duty Programs." The requirements in 10 CFR Part 26, Subpart I, of the final rule specifically address managing worker fatigue by designating individual break requirements, work hour limits, and annual reporting requirements.

As discussed in the Federal Register notice for the final rule (March 31, 2008, 73 FR 16966), Subpart I must be implemented by licensees no later than October 1, 2009. 3.0 TECHNICAL EVALUATION Subpart I of 10 CFR Part 26 strengthens requirements for both work hour controls and fatigue management.

Requirements in the rule include work hour limitations for rolling 24-hour, 48-hour, and 7-day periods. The rule also includes a required minimum break between work periods and varying required minimum days off. Additionally, Subpart I includes restrictions on the granting of waivers of the work hour controls. To grant a waiver, licensee management must determine that the waiver is necessary to mitigate or prevent a condition adverse to safety, is necessary to maintain site security, and there is reasonable assurance that the individual will be able to safely and competently perform his or her duties during the additional work period for which the waiver is granted. The proposed changes would delete administrative controls (which were based on GL 82-12) from the TSs to support the implementation of Subpart I of 10 CFR Part 26. The requirements established by 10 CFR Part 26, Subpart I, supersede the guidance in GL 82-12. Upon implementation of the proposed amendments, federal regulations would govern the requirements associated with work hour controls and fatigue management at Hope Creek and Salem Unit Nos. 1 and 2.

Since work hour controls and fatigue management requirements have been incorporated into the NRC's regulations, it is unnecessary to have work hour control requirements based on GL 82-12 in the TSs. As such, the NRC staff concludes that the proposed amendments are acceptable.

4.0 STATE

CONSUL TAT/ON In accordance with the Commission's regulations, the New Jersey State Officials were notified of the proposed issuance of the amendments. The State officials had no comments.

5.0 ENVIRONMENTAL

CONSIDERATION The amendments change record keeping, reporting, or administrative procedures or requirements.

Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(1 O)(ii). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

-3

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public. Principal Contributors: K. Martin R. Ennis Date: May 14, 2009 May 14, 2009 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear P.O. Box 236, N09 Hancocks Bridge, NJ 08038 HOPE CREEK GENERATING STATION AND SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 -

ISSUANCE OF AMENDMENTS RE: DELETION OF TECHNICAL SPECIFICATION REQUIREMENTS RELATED TO PLANT STAFF WORKING HOURS (TAC NOS. MD9309, MD9310 AND MD9311)

Dear Mr. Joyce:

The Commission has issued the enclosed Amendment No. 177 to Facility Operating License (FOL) No. NPF-57 for the Hope Creek Generating Station (Hope Creek) and Amendment Nos. 290 and 274 to FOL Nos.

DPR-70 and DPR-75 for the Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2. The amendments delete the requirements related to plant staff working hours from Section 6.0, "Administrative Controls" of the respective plants' Technical Specifications (TSs) in response to your application dated July 21, 2008. The requirements being deleted had been incorporated into the TSs based on the guidance in Generic Letter (GL) 82-12, "Nuclear Power Plant Staff Working Hours." The guidance in GL 82-12 has been superseded by the requirements in Title 10 of the Code of Federal Regulations (10 CFR), Part 26, "Fitness for Duty Programs," Subpart I, "Managing Fatigue." A copy of our safety evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice. Sincerely, /raj Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-354, 50-272 and 50-311

Enclosures:

1. Amendment No. 177 to License No. NPF-57

2. Amendment No. 290 to License No. DPR-70

3. Amendment No. 274 to License No. DPR-75

4. Safety Evaluation cc w/encls: Distribution via ListServ DISTRIBUTION PUBLIC RidsOgcRp Resource LPL1-2 RIF RidsAcrsAcnw_MailCTR Resource RidsNrrDorlLpl1-2 Resource RidsNrrDirsltsb Resource RidsNrrLAABaxter Resource RidsRgn1 MailCenter Resource RidsNrrPMREnnis Resource GHill (2), OIS RidsNrrDorlDpr Resource KMartin, NRRIDIRS/IOLB ADAMS Accession No* ML090860966 OFFICE LPL1-2/PM LPL 1-2/LA 10LB/BC OGC LPL 1-2/BC NAME REnnis ABaxter NSalgado AJones (NLO wi coments that must be addressed)

HChernoff DATE 4/13/09 4/14/09 4/16/09 4/28/09 5/14/09 OFFICIAL RECORD