ML110190268
| ML110190268 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  (NPF-069) |
| Issue date: | 01/31/2011 |
| From: | Richard Guzman Plant Licensing Branch 1 |
| To: | Belcher S Nine Mile Point |
| Guzman R, NRR/DORL, 415-1030 | |
| References | |
| TAC ME2972 | |
| Download: ML110190268 (12) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 31, 2011 Mr. Samuel L. Belcher Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT NO.2-ISSUANCE OF AMENDMENT REGARDING REMOVAL OF OPERATING MODE RESTRICTIONS FOR PERFORMING SURVEILLANCE TESTING OF THE DIVISION 3 BATTERY (TAC NO. ME2972)
Dear Mr. Belcher:
The Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 136 to Renewed Facility Operating License No. NPF-69 for the Nine Mile Point Nuclear Station (NMPNS), Unit No.2 (NMP2), in response to your application dated December 9.2009 (Agencywide Documents Access Management System (ADAMS) Accession No. ML093500090).
This amendment modifies the NMP2 Technical Specification (TS) 3.8.4, "DC Sources Operating," to remove the Mode restrictions for performance of TS Surveillance Requirements (SRs) 3.8.4.7 and 3.8.4.8 for the Division 3 direct current (DC) electrical power subsystem battery. The Division 3 DC electrical power subsystem feeds emergency DC loads associated with the high-pressure core spray (HPCS) system. These surveillances verify that the battery capacity is adequate for the battery to perform its required functions. The amendment removes these Mode restrictions for the Division 3 battery, thereby allowing performance of the SRs during Mode 1, 2, or 3 in conjunction with scheduled HPCS system outages.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.
Sincerely, Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410
Enclosures:
- 1. Amendment No. 136 to NPF-69
- 2. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NINE MILE POINT NUCLEAR STATION, LLC (NMPNS)
DOCKET NO. 50-410 NINE MILE POINT NUCLEAR STATION, UNIT NO.2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 136 Renewed License No. NPF-69
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A The application for amendment by Nine Mile Point Nuclear Station, LLC (the licensee) dated December 9,2009, 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; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
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; D.
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 E.
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.
- 2.
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 Renewed Facility Operating License No. NPF-69 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. 136 are hereby incorporated into this license.
Nine Mile Point Nuclear Station, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 2
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/l
(~.~
____~..P;' /::;+-a/z-- _/"'
ncy L. Salgado, Chief
~
C lant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the License and Technical Specifications Date of Issuance:
January 31, 2011
ATTACHMENT TO LICENSE AMENDMENT NO. 136 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-69 DOCKET NO. 50-410 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Page Insert Page 4
4 Replace the following pages of Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages Insert Pages 3.8.4-3 3.8.4-3 3.8.4-4 3.8.4-4
-4 (1)
Maximum Power Level Nine Mile Point Nuclear Station, LLC is authorized to operate the facility at reactor core power levels not in excess of 3467 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. 136 are hereby incorporated into this license. Nine Mile Point Nuclear Station, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Fuel Storage and Handling (Section 9.1, SSER 4)*
- a.
Fuel assemblies, when stored in their shipping containers, shall be stacked no more than three containers high.
- b.
When not in the reactor vessel, no more than three fuel assemblies shall be allowed outside of their shipping containers or ston~ge racks in the New Fuel Vault or Spent Fuel Storage Facility.
- c.
The above three fuel assemblies shall maintain a minimum edge to-edge spacing of twelve (12) inches from the shipping container array and approved storage rack locations.
- d.
The New Fuel Storage Vault shall have no more than ten fresh fuel assemblies uncovered at anyone time.
(4)
Turbine System Maintenance Program (Section 3.5.1.3.10, SER)
The operating licensee shall submit for NRC approval by October 31, 1989, a turbine system maintenance program based on the manufacturer's calculations of missile generation probabilities.
(Submitted by NMPC letter dated October 30, 1989 from C.D. Terry and approved by NRC letter dated March 15, 1990 from Robert Martin to Mr. Lawrence Burkhardt, III).
The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report (SER) and/or its supplements wherein the license condition is discussed.
Rene'Ned License No. NPF 69 Amendment 117 through 125, 126, 127, 128, 129, 130, 131, 132, 133, 134, 135 136
DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.4.6 Verify each required Division 1 and 2 battery charger supplies 2:: 300 amps and the required Division 3 battery charger supplies 2:: 40 amps at 2:: 130 V for 2:: 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
24 months SR 3.8.4.7
NOTES ---------------------------
- 1.
The modified performance discharge test in SR 3.8.4.8 may be performed in lieu of the service test in SR 3.8.4. 7 provided the modified performance discharge test completely envelops the service test.
- 2.
This Surveillance shall not be performed in MODE 1, 2, or 3 (not applicable to Division 3). However, credit may be taken for unplanned events that satisfy this SR.
Verify battery capacity is adequate to supply, and maintain in OPERABLE status, the required emergency loads for the design duty cycle when subjected to a battery service test.
24 months (continued)
NMP2 3.8.4-3 Amendment Q4~ 36
DC Sources - Operating 3.8.4 SURVEILLANCE SR 3.8.4.8
NOlrE----------------------------
lrhis Surveillance shall not be performed in MODE 1,2, or 3 (not applicable to Division 3).
However, credit may be taken for unplanned events that satisfy this SR Verify battery capacity is ~ 80% of the manufacturer's rating when subjected to a performance discharge test or a modified performance discharge test.
FREQUENCY 60 months 12 months when battery shows degradation or has reached 85%
of expected life with capacity
< 100% of manufacturer's rating 24 months when battery has reached 85% of the expected life with capacity
~ 100% of manufacturer's rating NMP2 3.8.4-4 Amendment 94, 136
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 136 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-69 NINE MILE POINT NUCLEAR STATION, LLC NINE MILE POINT NUCLEAR STATION, UNIT NO.2 DOCKET NO. 50-410
1.0 INTRODUCTION
By letter dated December 9, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML093500090), Nine Mile Nuclear Station, LLC (NMPNS or the licensee) submitted a license amendment request (LAR) for changes to the Nine Mile Point, Unit No.2 (NMP2) Technical Specifications (TSs). The proposed amendment would modify the NMP2 TS 3.8.4, "DC Sources - Operating," to remove the Mode restrictions for performance of TS Surveillance Requirements (SRs) 3.8.4.7 and 3.8.4.8 for the Division 3 direct current (DC) electrical power subsystem battery. The Division 3 DC electrical power subsystem feeds emergency DC loads associated with the high-pressure core spray (HPCS) system. These surveillances verify that the battery capacity is adequate for the battery to perform its required functions. The amendment would remove these Mode restrictions for the Division 3 battery, thereby allowing performance of the SRs during Mode 1, 2, or 3 in conjunction with scheduled HPCS system outages.
The licensee stated that reason for the amendment is to provide greater flexibility in scheduling Division 3 battery testing activities by allowing the testing to be performed during non-outage times. Having a completely tested Division 3 battery available for the duration of a refueling outage will reduce the number of system re-alignments and operator workload during an outage, and can provide reductions in outage critical path time.
In Section 4.2 of the LAR, the licensee stated that U.S. Nuclear Regulatory Commission (NRC) has approved similar license amendments to remove operating mode restrictions for performing HPCS battery surveillance testing. Recent examples include River Bend Station, amendment approved on August 12, 2004 (ADAMS Accession No. ML042300415) and Grand Gulf Nuclear Station, amendment approved on October 27,2003 (ADAMS Accession No. ML033030330).
2.0 REGULATORY EVALUATION
The following NRC requirements are applicable to the NRC staffs review of the licensee's amendment request:
- 2 Title 10 of the Code of Federal Regulations (10 CFR), Appendix A of Part 50, General Design Criterion (GDC) 17, "Electric power systems," requires, in part, that "An on site electric power system and an offsite electric power system shall be provided to permit functioning of structures, systems, and components important to safety... The on site electric power supplies, including the batteries, and the onsite electric distribution system, shall have sufficient independence, redundancy, and testability to perform their safety functions assuming a single failure..."
10 CFR Appendix A of Part 50, GDC 18, "Inspection and testing of electric power systems,"
requires that electric power systems that are important to safety must be designed to permit appropriate periodic inspection and testing.
10 CFR 50.36, "Technical specifications," requires a licensee to establish limiting conditions for operation, which include Completion Times for equipment that is required for safe operation of the facility.
3.0 TECHNICAL EVALUATION
3.1 Description of NMP2 Class 1 E DC Distribution System The NMP2 DC electrical power system is described in Section 8.3.2 of the NMP2 Updated Safety Analysis Report (USAR). The DC electrical power system, consisting of three independent 125 volt (V) DC Class 1 E subsystems (Divisions 1,2, and 3), is designed to provide the alternating current emergency power system with control power and power to safety-related equipment. DC loads are normally powered from the battery chargers, each of which is sized to charge a discharged battery while supplying normal steady state DC loads. Upon loss of normal power to the battery charger, the DC loads are automatically powered from the associated battery. Each division is located physically and electrically separate from the other divisions to ensure that a single failure does not cause failures in redundant divisions. There is no sharing between the redundant Class 1 E divisions and the independence of the three divisions is maintained throughout the distribution system and the DC loads.
The Division 3 DC electrical power subsystem provides reliable, continuous 125 V DC power for the HPCS system DC loads only (No Division 1 or 2 loads). Those loads include the emergency diesel generator controls and protection, 4.16 kilo-volt breaker control, power for the HPCS system logic, and all other related controls.
The Division 3 battery is sized to have adequate capacity to supply the required DC load profile continuously for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
TS SRs 3.8.4.7 and 3.8.4.8 require service discharge tests and performance discharge tests be performed periodically for each of the Division 1, 2, and 3 batteries. The battery service discharge test verifies the battery's capability to satisfy the design battery duty cycle of the DC electrical power system. The service discharge test (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in duration for Division 3 duty cycle) ensures that design duty cycle requirements, as specified in the NMP2 USAR, can be supplied by the Division 3 battery. The battery performance discharge test verifies adequate capacity of the battery and also provides an indication of the health of the battery. According to the licensee, these SRs can be completed within 38 hours4.398148e-4 days <br />0.0106 hours <br />6.283069e-5 weeks <br />1.4459e-5 months <br />. The HPCS system TS allowed outage time is 14 days in Modes 1,2, and 3, which provides more than enough time to complete SRs 3.8.4.7 and 3.8.4.8.
- 3 3.2 Evaluation of Proposed Changes The NRC staff reviewed the LAR and the design of the NMP2 125 V DC subsystem as described in the NMP2 USAR and has determined that as required by GDC 17, the DC electrical power system is designed to have sufficient independence, redundancy, and testability to perform its safety functions, assuming a single failure. Because the three divisions are physically and electrically separated and independent, testing and inspection of Division 3 is acceptable since it can be done without adversely affecting the other divisions, satisfying the requirements of GDC 18. In addition, this SR mode restriction change will not affect the subsystem's independence, redundancy or testability since the change is only to allow SR testing in Modes 1, 2, and 3, coincident with an HPCS system outage. As a result, the battery testing does not increase unavailability of the supported system (HPCS). Based on this information, the NRC staff finds this change acceptable with respect to GDCs 17 and 18.
The NRC staff reviewed the LAR and the NMP2 USAR with respect to the requested SR mode restriction changes and the requirements of 10 CFR 50.36. The requested change would allow SR testing of the Division 3 subsystem battery in Modes 1, 2, and 3. The TS-required frequencies for performing these SR tests are not being changed by the LAR. As stated by the licensee, the time needed to perform SR testing of the Division 3 subsystem battery is approximately 38 hours4.398148e-4 days <br />0.0106 hours <br />6.283069e-5 weeks <br />1.4459e-5 months <br />. Thus, the HPCS system 14-day (336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br />) TS allowed outage time (AOT) provides sufficient time to perform the SRs within the HPCS system AOT. Based on this information, the NRC staff finds this change acceptable with respect to 10 CFR 50.36 requirements.
3.2.3 Conclusion The NRC staff evaluated the licensee's proposed changes to SRs associated with the NMP2 Division 3 HPCS 125 V DC system battery. The changes would remove mode restrictions on SR 3.8.4.7 and SR 3.8.4.8 currently prohibited to be performed in Modes 1,2, or 3 as applicable to the 125 V DC system of Division 3. Based on the above technical evaluation, the NRC staff concludes that the proposed SR changes will not adversely impact the licensee's ability to continue comply with the requirements of 10 CFR 50.36, GDC 17, and GDC 18. Therefore, the NRC staff considers the proposed changes acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes SRs.
The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (April 6, 2010 (75 FR 17444)). Accordingly, the amendment meets the eligibility criteria
- 4 for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
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 amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: K. Miller Date: January 31, 2011
January 31, 2011 Mr. Samuel L. Belcher Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT NO.2-ISSUANCE OF AMENDMENT REGARDING REMOVAL OF OPERATING MODE RESTRICTIONS FOR PERFORMING SURVEILLANCE TESTING OF THE DIVISION 3 BATTERY (TAC NO. ME2972)
Dear Mr. Belcher:
The Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 136 to Renewed Facility Operating License No. NPF-69 for the Nine Mile Point Nuclear Station (NMPNS), Unit No.2 (NMP2), in response to your application dated December 9. 2009 (Agencywide Documents Access Management System (ADAMS) Accession No. ML093500090).
This amendment modifies the NMP2 Technical Specification (TS) 3.8.4, "DC Sources Operating," to remove the Mode restrictions for performance of TS Surveillance Requirements (SRs) 3.8.4.7 and 3.8.4.8 for the Division 3 direct current (DC) electrical power subsystem battery. The Division 3 DC electrical power subsystem feeds emergency DC loads associated with the high-pressure core spray (HPCS) system. These surveillances verify that the battery capacity is adequate for the battery to perform its required functions. The amendment removes these Mode restrictions for the Division 3 battery, thereby allowing performance of the SRs during Mode 1,2, or 3 in conjunction with scheduled HPCS system outages.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.
Sincerely,
/raj Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410
Enclosures:
- 1. Amendment No. 136 to NPF-69
- 2. Safety Evaluation cc w/encls: Distribution via Listserv Distribution:
PUBLIC RidsOgcRp RidsOGCMailCenter RidsNrrDeEeeb LPL1-1 RtF RidsNrrDorlLPL1-1 RidsNrrLASLitlle RidsRgn1 MailCenter RidsAcrsAcnw_MailCenter RidsNrrDirsltsb RidsNrrDorlDpr RidsNrrPMNineMilePoint KMiller, NRR GWaig, NRR ADAMS Accession No.: ML110190268
- SE provided by memo. No substantial changes made. **Concurrence via e-mail NRR-106
)FFICE LPL 1-1/PM LPL1-1/LA DE/EEEB/BC(A)
DIRS/ITSB/BC OGC LPL1-1/BC
\\lAME RGuzman SUttle**
RMathew*
RElliott LSubin NSalgado (.IBoska for)
)ATE 1/21/11 1/21/11 1/20/11 1/24/11 1/26/11 1/31/11 OFFICIAL RECORD COpy