ML050630310
| ML050630310 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 06/15/2005 |
| From: | Nerses V NRC/NRR/DLPM/LPD1 |
| To: | Peschel J, Warner M Florida Power & Light Energy Seabrook |
| Nerses V, NRR//DLPM, 415-1484 | |
| References | |
| TAC MC4902 | |
| Download: ML050630310 (11) | |
Text
June 15, 2005 Mr. Mark E. Warner, Site Vice President c/o James M. Peschel Seabrook Station FPL Energy Seabrook, LLC PO Box 300 Seabrook, NH 03874
SUBJECT:
SEABROOK STATION, UNIT NO. 1 - ISSUANCE OF AMENDMENT RE: REVISION TO TECHNICAL SPECIFICATIONS RELATED TO ALLOWED OUTAGE TIMES FOR ACCIDENT MONITORING INSTRUMENTATION (TAC NO. MC4902)
Dear Mr. Warner:
The Commission has issued the enclosed Amendment No. 103 to Facility Operating License No. NPF-86 for the Seabrook Station, Unit No. 1 (Seabrook), in response to your application dated October 22, 2004, as supplemented by letter dated December 16, 2004.
The amendment revises the Seabrook Technical Specification 3/4.3.3.6 to allow for individual entry into the limiting condition for operation (LCO) for each instrument, and extends the allowed outage times for LCOs 3.3.3.6.a and 3.3.3.6.b.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
Victor Nerses, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-443
Enclosures:
- 1. Amendment No. 103 to License No. NPF-86
- 2. Safety Evaluation cc w/encls: See next page
Seabrook Station, Unit No. 1 cc:
Mr. J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Peter Brann Assistant Attorney General State House, Station #6 Augusta, ME 04333 Resident Inspector U.S. Nuclear Regulatory Commission Seabrook Nuclear Power Station P.O. Box 1149 Seabrook, NH 03874 Town of Exeter 10 Front Street Exeter, NH 03823 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Office of the Attorney General One Ashburton Place, 20th Floor Boston, MA 02108 Board of Selectmen Town of Amesbury Town Hall Amesbury, MA 01913 Ms. Deborah Bell Federal Emergency Management Agency Region I J.W. McCormack P.O. &
Courthouse Building, Room 401 Boston, MA 02109 Mr. Tom Crimmins Polestar Applied Technology One First Street, Suite 4 Los Altos, CA 94019 Mr. Stephen McGrail, Director ATTN: James Muckerheide Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399 Philip T. McLaughlin, Attorney General Steven M. Houran, Deputy Attorney General 33 Capitol Street Concord, NH 03301 Mr. Bruce Cheney, Director New Hampshire Office of Emergency Management State Office Park South 107 Pleasant Street Concord, NH 03301 Mr. Gene F. St. Pierre Station Director Seabrook Station FPL Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874 Mr. M. S. Ross, Managing Attorney Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Rajiv S. Kundalkar Vice President - Nuclear Engineering Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 James M. Peschel Regulatory Programs Manager Seabrook Station FPL Energy Seabrook, LLC PO Box 300 Seabrook, NH 03874
Seabrook Station, Unit No. 1 cc:
David Moore Vice President, Nuclear Operations Support Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Marjan Mashhadi Senior Attorney Florida Power & Light Company 801 Pennsylvania Ave., NW Suite 220 Washington, DC 20004
Mr. Mark E. Warner, Site Vice President c/o James M. Peschel Seabrook Station FPL Energy Seabrook, LLC PO Box 300 Seabrook, NH 03874
SUBJECT:
SEABROOK STATION, UNIT NO. 1 - ISSUANCE OF AMENDMENT RE: REVISION TO TECHNICAL SPECIFICATIONS RELATED TO ALLOWED OUTAGE TIMES FOR ACCIDENT MONITORING INSTRUMENTATION (TAC NO. MC4902)
Dear Mr. Warner:
The Commission has issued the enclosed Amendment No. 103 to Facility Operating License No. NPF-86 for the Seabrook Station, Unit No. 1 (Seabrook), in response to your application dated October 22, 2004, as supplemented by letter dated December 16, 2004.
The amendment revises the Seabrook Technical Specification 3/4.3.3.6 to allow for individual entry into the limiting condition for operation (LCO) for each instrument, and extends the allowed outage times for LCOs 3.3.3.6.a and 3.3.3.6.b.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
Victor Nerses, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-443
Enclosures:
- 1. Amendment No. 103 to License No. NPF-86
- 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION PUBLIC DRoberts RDennig BMarcus GHill (2)
PDI-2 R/F VNerses EMarinos ACRS DLPM DPR GMiller CHolden CRaynor TBoyce OGC GMatakas, RGN-I Accession Numbers: SE, ML050630310; TSs, ML000000000; Package, ML050630319 OFFICE PDI-2/PE PDI-2/PM PDI-2/LA EEIB-A/SC NAME GMiller VNerses CRaynor EMarinos DATE 5/12/05 5/16/05 5/12/05 2/23/05 OFFICE IROB-A/SC OGC PDI-2/SC NAME TBoyce KKannler DRoberts DATE 5/9/05 5/19/05 6/14/05 OFFICIAL RECORD COPY
FPL ENERGY SEABROOK, LLC, ET AL.*
DOCKET NO. 50-443 SEABROOK STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 103 License No. NPF-86 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by FPL Energy Seabrook, LLC, et al. (the licensee), dated October 22, 2004, as supplemented by letter dated December 16, 2004, 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.
- FPL Energy Seabrook, LLC (FPLE Seabrook), is authorized to act as agent for the following:
Hudson Light & Power Department, Massachusetts Municipal Wholesale Electric Company, and Taunton Municipal Light Plant. FPLE Seabrook has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
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 Facility Operating License No. NPF-86 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 103, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA by DCollins for/
Darrell J. Roberts, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 15, 2005
ATTACHMENT TO LICENSE AMENDMENT NO. 103 FACILITY OPERATING LICENSE NO. NPF-86 DOCKET NO. 50-443 Replace the following pages of the Appendix A, Technical Specifications, with the attached revised pages as indicated. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert 3/4 3-49 3/4 3-49 3/4 3-49a B 3/4 3-5 B 3/4 3-5 B 3/4 3-6 B 3/4 3-6 B 3/4 3-7
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 103 TO FACILITY OPERATING LICENSE NO. NPF-86 FPL ENERGY SEABROOK, LLC SEABROOK STATION, UNIT NO. 1 DOCKET NO. 50-443
1.0 INTRODUCTION
By letter dated October 22, 2004, as supplemented by letter dated December 16, 2004, FPL Energy Seabrook, LLC (FPLE Seabrook) submitted a request to revise the Seabrook Station, Unit No. 1 (Seabrook) Technical Specifications (TSs). The proposed change would revise the allowed outage times (AOTs) and associated action requirements for certain accident monitoring instrumentation in TS 3/4.3.3.6, Accident Monitoring Instrumentation. Additionally, the proposed revision would allow individual entry into an action statement for each instrument (also referred to as function).
2.0 REGULATORY EVALUATION
Section 50.36(c)(2)(i) of Title 10 of the Code of Federal Regulations (10 CFR) states, in part:
Limiting conditions for operation [LCOs] are the lowest functional capability or performance levels of equipment required for safe operation of the facility.
When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow remedial action permitted by the technical specifications until the condition can be met.
The remedial actions and required completion times delineated in the TSs minimize the potential impact of an unnecessary transient while still requiring that the plant be moved to a safe condition in a time-frame commensurate with the safety significance of the inoperable system.
3.0 TECHNICAL EVALUATION
In its submittal, FPLE Seabrook stated that the current AOTs specified in TS 3/4.3.3.6 do not allow adequate time to implement online repairs to certain accident monitoring instrumentation when required, and that these AOTs could present unnecessary burdens during maintenance and plant betterment activities. Additionally, FPLE Seabrook proposed the addition of a note allowing individual entry into an action statement for each instrument. FPLE Seabrook further stated that the proposed changes were consistent with NUREG-1431, Revision 3, Standard Technical Specifications, Westinghouse Plants.
3.1 Action Statement a The licensee proposed revising Action 3.3.3.6.a, which is applicable to all functions in TS Table 3.3-10, as follows:
With the number of OPERABLE accident monitoring instrumentation channels less than the Total Number of Channels shown in Table 3.3-10, restore the inoperable channel(s) to OPERABLE status within 730 days, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The provisions of Specification 3.0.4 are not applicable. submit a Special Report to the Commission pursuant to Specification 6.8.2 within the next 14 days outlining the preplanned alternate method of monitoring, the cause of inoperability, and the plans and schedule for restoring the instrumentation to OPERABLE status.
This change would extend the required action time for Action 3.3.3.6.a from 7 to 30 days and change the required action from shutting down the unit to submitting a report to the Nuclear Regulatory Commission (NRC or the Commission).
During the development of the Standard Technical Specifications (STS), it was determined that the 7-day completion time was overly restrictive. The STS extended the completion time for one inoperable instrument channel from 7 days to 30 days. This extension was based on operating experience, the operability of the remaining channels, the passive nature of the instruments (i.e., the instruments do not initiate critical automatic actions), and the low probability of an event requiring the accident monitoring instrumentation during this interval.
The proposed submission of a special report within 14 days in lieu of a plant shutdown is appropriate because the report would formally document compensatory actions in place during the instrument outage, while avoiding an unnecessary plant transient. The NRC staff finds that the proposed modification of Action 3.3.3.6.a will continue to meet the requirements of 10 CFR 50.36(c)(2)(i) and is, therefore, acceptable.
3.2 Action Statement b The licensee proposed revising Action 3.3.3.6.b, which is applicable to all functions in TS Table 3.3-10, as follows:
With the number of OPERABLE accident monitoring instrumentation channels except the containment POST-LOCA [loss-of-coolant accident] high range area monitor, less than the Minimum Channels OPERABLE requirements of Table 3.3-10, restore the inoperable channel(s) to OPERABLE status within 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />s7 days or be in at lease HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at lease HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The provisions of Specification 3.0.4 are not applicable.
This change would extend the required action time for Action 3.3.3.6.b from 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to 7 days.
As discussed in the FPLE Seabrooks December 16, 2004 supplement, and independently verified by the NRC staff, the following conditions are shared by the Seabrook TSs and the STS:
Instrument operability Applicability in MODES 1, 2, and 3 for all instruments The action statement is excepted from the application of LCO 3.0.4 A channel check is required to be performed at least once per 31 days and a channel calibration is required at least once per 18 months Given that the LCO, its applicability, and surveillance requirements (SRs) are reasonably similar to the STS, consistency with the STS is an acceptable justification for the change. Additionally, FPLE Seabrook stated that there is a relatively low probability of an event requiring reliance on the instrumentations. The NRC staff finds the proposed change to Action 3.3.3.6.b will continue to meet the requirements of 10 CFR 50.36(c)(2)(i) and is, therefore, acceptable.
3.3 TS 3/4.3.3.6 Note FPLE Seabrook proposed to add the following note to TS 3/4.3.3.6:
A separate ACTION entry is allowed for each INSTRUMENT listed in Table 3.3-10 A function is referred to as an instrument in TS 3/4.3.3.6. The current LCO for TS 3/4.3.3.6 does not discuss how multiple inoperable instrument channels of different functions are tracked.
The new note would allow the action statement of LCO 3.3.3.6 to be entered independently for each function. The AOT for each inoperable channel of a function would be tracked separately for each function, starting from the time the action was entered for that particular function.
As discussed in Section 3.2 of this Safety Evaluation, the Seabrook TS 3/4.3.3.6 is reasonably similar to the equivalent STS LCO, applicability, and SRs, and as such, consistency with the STS is an acceptable justification for the change. Therefore, the NRC staff finds the proposed change to be acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the New Hampshire and Massachusetts State officials were notified of the proposed issuance of the amendment. The State officials had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes the TSs. 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 (69 FR 63560). Accordingly, the amendment meets the eligibility criteria 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: B. Marcus Date: June 15, 2005