ML021570380
| ML021570380 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/24/2002 |
| From: | Nerses V NRC/NRR/DLPM/LPD1 |
| To: | Rice J, Danni Smith Dominion Nuclear Connecticut |
| Nerses V, NRR//DLPM, 415-1484 | |
| References | |
| TAC MB4011 | |
| Download: ML021570380 (16) | |
Text
July 24, 2002 Mr. J. A. Price Vice President - Nuclear Technical Services - Millstone Dominion Nuclear Connecticut, Inc.
Mr. David A. Smith Rope Ferry Road Waterford, CT 06385
SUBJECT:
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 - ISSUANCE OF AMENDMENT RE: CHANGE SURVEILLANCE REQUIREMENTS TO ONCE PER 24 MONTHS (TAC NO. MB4011)
Dear Mr. Price:
The Commission has issued the enclosed Amendment No. 206 to Facility Operating License No. NPF-49 for the Millstone Nuclear Power Station, Unit No. 3, in response to your application dated February 5, 2002, as supplemented on March 6, 2002.
The amendment changes the term in the Technical Specifications once each REFUELING INTERVAL to once per 24 months in several surveillance requirements.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Victor Nerses, Sr. Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosures:
- 1. Amendment No. 206 to NPF-49
- 2. Safety Evaluation cc w/encls: See next page
July 24, 2002 Mr. J. A. Price Vice President - Nuclear Technical Services - Millstone Dominion Nuclear Connecticut, Inc.
Mr. David A. Smith Rope Ferry Road Waterford, CT 06385
SUBJECT:
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 - ISSUANCE OF AMENDMENT RE: CHANGE SURVEILLANCE REQUIREMENTS TO ONCE PER 24 MONTHS (TAC NO. MB4011)
Dear Mr. Price:
The Commission has issued the enclosed Amendment No. 206 to Facility Operating License No. NPF-49 for the Millstone Nuclear Power Station, Unit No. 3, in response to your application dated February 5, 2002, as supplemented on March 6, 2002.
The amendment changes the term in the Technical Specifications once each REFUELING INTERVAL to once per 24 months in several surveillance requirements.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Victor Nerses, Sr. Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosures:
- 1. Amendment No. 206 to NPF-49
- 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC OGC PDI-2 R/F ACRS SRichards TClark CCowgill, RI GHill (2)
RDennig JZimmerman VNerses Accession No.: ML021570380
- See previous concurrence OFFICE PDI-2/PM PDI-2/LA PDI-2/PM RORP
- PDI-2/SC NAME RPulsifer TLClark REnnis for VNerses RDennig RHoefling JZimmerman DATE 7/23/02 7/23/02 7/23/02 6/18/02 7/2/02 7/23/02 OFFICIAL RECORD COPY
Millstone Nuclear Power Station Unit 3 cc:
Ms. L. M. Cuoco Senior Nuclear Counsel Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Edward L. Wilds, Jr., Ph.D.
Director, Division of Radiation Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 First Selectmen Town of Waterford 15 Rope Ferry Road Waterford, CT 06385 Mr. P. J. Parulis Manager - Nuclear Oversight Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. W. R. Matthews Vice President and Senior Nuclear Executive - Millstone Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Ernest C. Hadley, Esquire P.O. Box 1104 West Falmouth, MA 02574-1104 Mr. John Markowicz Co-Chair Nuclear Energy Advisory Council 9 Susan Terrace Waterford, CT 06385 Mr. Evan W. Woollacott Co-Chair Nuclear Energy Advisory Council 128 Terrys Plain Road Simsbury, CT 06070 Mr. D. A. Christian Senior Vice President - Nuclear Operations and Chief Nuclear Officer Innsbrook Technical Center - 2SW 5000 Dominion Boulevard Waterford, CT 06385 Mr. C. J. Schwarz Director -Nuclear Station Operations and Maintenance Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Senior Resident Inspector Millstone Nuclear Power Station c/o U.S. Nuclear Regulatory Commission P. O. Box 513 Niantic, CT 06357 Mr. G. D. Hicks Director - Nuclear Station Safety and Licensing Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. J. Alan Price Site Vice President - Millstone c/o Mr. David A. Smith Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385
Millstone Nuclear Power Station Unit 3 cc:
Mr. D. A. Smith Manager - Licensing Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Ms. Nancy Burton 147 Cross Highway Redding Ridge, CT 00870 Mr. William D. Meinert Nuclear Engineer Massachusetts Municipal Wholesale Electric Company P.O. Box 426 Ludlow, MA 01056 Mr. S. E. Scace Director - Nuclear Engineering Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385 Mr. M. J. Wilson Manager - Nuclear Training Dominion Nuclear Connecticut, Inc.
Rope Ferry Road Waterford, CT 06385
DOMINION NUCLEAR CONNECTICUT, INC., ET AL.
DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 206 License No. NPF-49
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the applicant dated February 5, 2002, as supplemented on March 6, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 Commissions 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 Commissions 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 Facility Operating License No. NPF-49 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 206, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license.
Dominion Nuclear Connecticut, Inc. shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of the date of issuance, and shall be implemented within 90 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Jacob I. Zimmerman, Acting 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: July 24, 2002
ATTACHMENT TO LICENSE AMENDMENT NO. 206 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following pages of the 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 Insert 3/4 1-24 3/4 1-24 3/4 1-25 3/4 1-25 3/4 4-13 3/4 4-13 3/4 4-21 3/4 4-21 3/4 4-23 3/4 4-23 3/4 4-39 3/4 4-39 3/4 5-4 3/4 5-4 3/4 5-5 3/4 5-5 3/4 5-10 3/4 5-10 3/4 6-12 3/4 6-12 3/4 6-13 3/4 6-13 3/4 6-15 3/4 6-15 3/4 6-17 3/4 6-17 3/4 6-19 3/4 6-19 3/4 6-20 3/4 6-20 3/4 6-22 3/4 6-22 3/4 7-5 3/4 7-5 3/4 7-11 3/4 7-11 3/4 7-12 3/4 7-12 3/4 7-16 3/4 7-16 3/4 7-19 3/4 7-19 3/4 7-20 3/4 7-20 3/4 7-21 3/4 7-21 3/4 7-23 3/4 7-23 3/4 9-13 3/4 9-13 3/4 9-14 3/4 9-14 B3/4 0-4 B3/4 0-4 B3/4 4-25 B3/4 4-25 B3/4 5-5 B3/4 5-5 B3/4 6-6 B3/4 6-6 B3/4 7-14 B3/4 7-14 B3/4 7-15 B3/4 7-15 B3/4 7-16 B3/4 7-16 B3/4 7-21 B3/4 7-21
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 206 TO FACILITY OPERATING LICENSE NO. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 DOCKET NO. 50-423
1.0 INTRODUCTION
By letter dated February 5, 2002, as supplemented March 6, 2002, the Dominion Nuclear Connecticut, Inc. (DNC), submitted a request for changes to the Millstone Nuclear Power Station, Unit No. 3 (MP3) Technical Specifications (TSs). The requested change would modify several surveillance requirements by replacing the term once each REFUELING INTERVAL with once per 24 months.
2.0 BACKGROUND
By letter dated May 1, 1995 (Ref. 1) a request was submitted by the licensee of MP3 to extend the interval for the performance of selected surveillances from 18 months to 24 months to coincide with a 24 month operating cycle for MP3. The pertinent TSs were changed to once each REFUELING INTERVAL and approved for an interval of 24 months. Several subsequent amendment requests were submitted to change other selected surveillances. Each of these requests was followed by a license amendment from the NRC approving the surveillance interval increase. These interval extensions were based on the review of historical plant maintenance and surveillance data. However, subsequent to these amendments and before all surveillances were changed from 18 months to 24 months DNC decided to return to an 18-month fuel cycle.
The Ref. 1 submittal specifically requested selected TSs that specify an 18-month surveillance to be changed to state that these surveillances are to be performed at least once each refueling interval (i.e., 24-months). Guidance on the proposed TS changes was provided by NRC Generic Letter (GL) 91-04, Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle, dated April 2, 1991. Licensees were advised in this GL to evaluate the results of the performance of the surveillance tests previously performed at the 18 month interval as well as maintenance records and other data, to justify any requested extension of the testing interval to 24 months +/-25 percent or a maximum of 30 months. The regulatory acceptance to change the testing frequency from once each REFUELING OUTAGE to once per 24 months is based on the criteria of GL 91-04 for accepting the proposed changes to TS surveillance requirements in order to accommodate a 24-month surveillance interval while still meeting the requirements of 10 CFR 50.36(c)(3). The safety evaluations of the applicable previous amendments as discussed in Section 3.0, were also used.
Amendment No. 122, dated December 28, 1995 (Ref. 2) issued a new Table 1.1, Frequency Notation, which defined R as REFUELING INTERVAL with a frequency of at least once per 24 months. Subsequently on October 2, 1997 (Ref. 3) the staff issued a correction to Amendment No. 122 which returned Table 1.1 back to its previous revision because all 18 month surveillances had not been justified to be extended to 24 months. The previous Table 1.1 defined R as a frequency of at least once per 18 months. Because of this correction to Amendment No. 122 the term REFUELING INTERVAL became undefined. This caused inconsistencies in the MP3 TSs because the term was no longer in the definition section of the TSs although it was used throughout the TSs, capitalized, as though it was a defined term.
The approved amendments resulted in surveillance requirements being approved for a 24-month interval, surveillance requirements in the TSs stating they were to be completed once per REFUELING INTERVAL which is now undefined and Table 1.1 indicating R is once per 18 months. The February 5, 2002, submittal requested that the term once each REFUELING INTERVAL be changed to once per 24 months so that there would be no inconsistency between Table 1.1 and selected surveillance requirements. There is one surveillance (SR 4.6.4.1.c) that will still refer to the term REFUELING INTERVAL which is an undefined term. The licensee will submit an amendment request to correct this inconsistency.
The GL noted that if the performance of a surveillance during plant operation would adversely affect safety, the licensee should postpone the surveillance until the plant is shutdown for refueling or in a condition or mode consistent with safe conduct of that surveillance. DNC had previously agreed with this position.
3.0 EVALUATION 3.1 Amendment No. 122 By letter dated December 28, 1995 (Ref. 2) the NRC issued Amendment No. 122 for MP3.
This amendment approved changes in surveillance frequency from 18 to 24 months by revising the words in the surveillance requirements (SR) from once per 18 months to once each REFUELING INTERVAL. The licensee proposes to now change the wording in the following SRs from once each REFUELING INTERVAL to once per 24 months: SR 4.1.3.3, Position Indicating System - Shutdown; 4.1.3.4.c, Rod Drop Time; 4.6.2.1.c, Containment Quench Spray System; 4.6.2.2.c and d, Recirculation Spray System; and 4.6.3.2, Containment Isolation Valves.
The staff found in Ref. 2 that the change in TS surveillance frequency from 18 to 24 months is acceptable for TS 4.1.3.3 because of the licensees review of their surveillance results, preventive maintenance records, and frequency and type of corrective maintenance, and the staffs review of agency records concerning digital rod position indication system performance.
Based on the licensees review of control rod drive system equipment performance and the staffs review of agency records for MP3 the staff concluded that the frequency of TS Surveillance Requirement 4.1.3.4.c from 18 to 24 months to be acceptable.
Regarding the extension of the frequency from 18 to 24 months for SRs 4.6.2.1.c, 4.6.2.2.c, and 4.6.2.2.d, Ref. 2 states that based on the engineering review of equipment performance, preventive, and corrective maintenance history and the availability of quarterly inservice testing, this change was acceptable.
For TS 4.6.3.2 in Ref. 2 the staff states that the extension from 18 to 24 months, based on the maintenance and performance history, the containment isolation valves are highly reliable and that the extension would not result in a deterioration in valve condition or performance, the change is acceptable.
Because the staff had reviewed and approved the wording change for SRs 4.1.3.3, 4.1.3.4, 4.6.2.1, 4.6.2.2, and 4.6.3.2 in Amendment No. 122 from once each 18 months to once each REFUELING INTERVAL based on an evaluation where the surveillance frequency would be at least once per 24 months, this change is acceptable.
3.2 Amendment No. 123 The NRC issued Amendment No. 123 for MP3 on December 28, 1995 (Ref. 4). This amendment approved changes in surveillance frequency from 18 to 24 months by revising the words in the SR from once per 18 months to once each REFUELING INTERVAL in SR 4.6.6.1.b and d, Supplementary Leak Collection and Release System (SLCRS); 4.7.7, Control Room Emergency Ventilation System, 4.7.8; Control Room Envelope Pressurization System; 4.7.9.b and d, Auxiliary Building Filter System (ABFS); and 4.9.12.1.b and d, Fuel Building Exhaust Filter System. SR 4.6.6.1.d.3 has subsequently been changed to SR 4.6.6.2.2 in a letter dated February 5, 1996 (Ref. 5). DNC now proposes to change the wording in the above SRs from once each REFUELING INTERVAL to once per 24 months.
The staff had found in Ref. 4 and in the Bases for the SLCRS (page B 3/4 6-6) that SR 4.6.6.1.b and d [SR 4.6.6.1.d.3 is now 4.6.6.2.2] that these surveillances have to be performed under conditions that apply during a plant outage. Ref. 4 stated that there is reasonable assurance that extending the frequency (to 24 months) of these surveillances will not degrade the ability of the SLCRS from performing its safety function; therefore, it is acceptable. It is understood as reflected in the Bases that changing once each REFUELING INTERVAL to once per 24 months for these surveillances does not preclude the fact that the surveillances will be performed under conditions that apply during a plant outage which is within the 24-month interval (MP3 is presently on an 18-month fuel cycle). Therefore, this change is acceptable.
For TSs 4.7.7 and 4.7.8 Ref. 4 states that based on surveillance results, there is reasonable assurance that extending the frequency (to 24 months) of these surveillances will not degrade the capability of the Control Room Emergency Ventilation, Filtration and Pressurization System to perform the intended functions and that the proposed extension was acceptable.
The staff had concluded in Ref. 4 that based on the surveillance test results and additional testing performed in 1993, there is reasonable assurance that extending the frequency (to 24 months) will not degrade the capability of the ABFS to perform its intended functions, therefore the extension was acceptable.
Based on surveillance results, according to Ref. 4, there is reasonable assurance that extending the frequency (to 24 months) of SRs 4.9.12.b and 4.9.12.d will not affect the capability of the Fuel Building Exhaust Filter System to perform the intended function when irradiated fuel with less than 60 days decay is in the spent fuel pool. Therefore, the proposed changes were acceptable.
Because the staff had reviewed and approved the wording change for SR 4.6.6.1.b and d [SR 4.6.6.1.d.3 is now 4.6.6.2.2], 4.7.7, 4.7.8, 4.7.9.b and d, and 4.9.12.1.b and d in Amendment No. 123 from once each 18 months to once each REFUELING INTERVAL based on an evaluation where the surveillance frequency would be at least once per 24 months, this change is acceptable.
3.3 Amendment No. 124 By letter dated December 28, 1995 (Ref. 6) the NRC issued Amendment No. 124 for MP3.
This amendment approved changes in SR 4.5.2.d, e, and g, Emergency Core Cooling Systems, and 4.5.5, pH Trisodium Phosphate [TSP] Storage Baskets, and changes in surveillance frequency from 18 to 24 months by changing the words in the SR from once per 18 months to once each REFUELING INTERVAL. The licensee proposes to now change the wording in the above SRs from once each REFUELING INTERVAL to once per 24 months.
Amendment No. 115 (Ref. 7), dated May 26, 1995, approved the wording change to once each REFUELING INTERVAL for SR 4.5.5 since access to the TSP baskets is only feasible during outages. Amendment No. 124 confirmed that the assessment for 4.5.5 took into account that the interval would likely be 24 months. As previously stated, the licensee agreed if needed, to postpone a surveillance until the plant is shut down for refueling or in a condition or mode consistent with safe conduct of the surveillance. Also in Amendment No. 124 the staff had reviewed and approved the wording change for SR 4.5.2.d, e, and g from once per 18 months to once each REFUELING INTERVAL based on an evaluation of records where the surveillance frequency would be at least once per 24 months. This change from once each REFUELING INTERVAL to once per 24 months does not modify the evaluation of Amendment Nos. 115 and 124 to test at a frequency of once per 24 months, therefore, is acceptable.
3.4 Amendment No. 127 By letter dated March 4, 1996 (Ref. 8) the NRC issued Amendment No. 127 for MP3. This amendment approved changes in surveillance frequency from 18 to 24 months by changing the words in the SR from once per 18 months to once each REFUELING INTERVAL in SR 4.6.4.2, Electric Hydrogen Recombiners; 4.7.1.2.1.c, Auxiliary Feedwater System; 4.7.3.b, Reactor Plant Component Cooling Water System; 4.7.4.b, Service Water System; and 4.7.10.e, Snubbers. The licensee proposes to now change the wording in the SRs from once each REFUELING INTERVAL to once per 24 months.
Ref. 8 approved the extension of surveillance requirement testing from 18 months to 24 months knowing that SR 4.6.4.2 must be performed during shutdown. The proposed change in wording from once each refueling interval to once per 24 months still assumes that the testing would be done during shutdown conditions. As previously stated, the licensee agreed if needed, to postpone a surveillance until the plant is shut down for refueling or in a condition or mode consistent with safe conduct of a surveillance. Because SR 4.6.4.2 had been approved for testing every 24 months and the licensee has agreed to do the surveillance in a condition or mode consistent with safe conduct of the surveillance and the present refueling cycle is within a 24-month interval, this change is acceptable.
SR 4.7.1.2.1.c was reviewed in Ref. 8 and the staff noted that by an Auxiliary Feedwater System (AFW) performance review, a quarterly cold start turbine-driven surveillance, as well as many overlapping requirements from other tests, that the extension of the testing time interval from 18 months to 24 months for SR 4.7.1.2.1.c was acceptable. Because of this previous approval, the proposed change from once each REFUELING INTERVAL to once per 24 months is acceptable.
Also in Ref. 8 the staff had reviewed the surveillance frequency for SR 4.7.3.b, Reactor Plant Component Cooling Water System (RPCCW). The review looked at past performance as well as preventative and corrective maintenance history of the system which indicated that there was no need to maintain an 18-month schedule and increasing to a 24-month schedule would not adversely affect the reliability of the system. The staff concluded that the extension of the testing time interval from 18 months to 24 months for SR 4.7.3.b was acceptable. Therefore, the surveillance frequency change from once each REFUELING INTERVAL to once each 24 months is acceptable.
A review of SR 4.7.4.b in Ref. 8 shows that preventative and corrective maintenance records along with a system performance review concluded that the extension of the testing interval from 18 months to 24 months was acceptable. The proposed change to the frequency of SR 4.7.4.b from once each REFUELING INTERVAL to once per 24 months is therefore, acceptable.
The staff concluded in Ref. 8 that the extension of the testing time interval from 18 months to 24 months for SR 4.7.10.e, Snubbers, is acceptable. This was based on the fact that both the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants (1990), subsection ISTD program and the proposed MP3 program were basically equivalent. A probabilistic risk assessment concluded that the proposed change is not risk significant. This surveillance is accomplished during an outage and the current refueling cycle of 18 months is within the proposed frequency of once per 24 months. As stated earlier the licensee agreed if needed, to postpone a surveillance until the plant is shut down for refueling or in a condition or mode consistent with safe conduct of a surveillance. Therefore, the surveillance frequency change from once each REFUELING INTERVAL to once per 24 months is acceptable.
Because the staff had previously reviewed and approved the wording change for SR 4.6.4.2, 4.7.1.2.1.c, 4.7.3.b, 4.7.4.b, and 4.7.10.e in Amendment No. 127 from once each 18 months to once each REFUELING INTERVAL based on an evaluation where the surveillance frequency would be at least once per 24 months, this change is acceptable.
3.5 Amendment No. 133 By letter dated February 19, 1997 (Ref. 9) the NRC issued Amendment No. 133 for MP3. This amendment approved in SR 4.4.4.1.a and 3, Relief Valves; 4.4.6.1, Leakage Detection Systems; 4.4.6.2.2, Operational Leakage; and 4.4.9.3.1.b, Overpressure Protection System; changes in surveillance frequency from 18 to 24 months by changing the words in the SR from once per 18 months to once each REFUELING INTERVAL. The licensee proposes to now change the wording in the above SRs from once each REFUELING INTERVAL to once per 24 months.
In Ref. 9 the staff evaluated an increase in the frequency of testing for SR 4.4.4.1.a and 4.4.9.3.1.b. These SRs verify the operability of power operated relief valves (PORV) by performance of a channel calibration. The staff concluded that through review of surveillance results, preventative maintenance records, and the frequency and type of corrective maintenance, that extending the testing time interval from 18 months to each refueling interval (24 months) was acceptable. The proposed change of the testing frequency from once each REFUELING INTERVAL to once per 24 months is, therefore, acceptable.
In Ref. 9 the staff approved the testing time extensions from 18 months to each refueling interval (24 months) for SR 4.4.4.1.b and 4.4.4.3. This approval was based on the review of surveillance and maintenance records and that there have been no failures of the PORVs or the block valves to operate and there was no indication of linear time dependant drift with regard to circuit components. It was also noted that SR 4.4.4.2 provides additional assurance that the block valves are operable. The previous approval was requested on the assumption that the refueling interval was 24 months. Because these TSs have been previously approved for a testing frequency of 24 months the proposed change from once each REFUELING INTERVAL to once per 24 months is acceptable.
SR 4.4.6.1.b requires that the containment drain sump level and pumped capacity monitoring system instrumentation be calibrated. A review of surveillance and maintenance records as stated in Ref. 9 was performed to determine the impact of extending the frequency of testing from 18 months to each refueling interval or 24 months. The review of past preventative maintenance and corrective maintenance activities did not identify any significant activities that were required to correct component failures and there was no indication of linear time dependant drift with regard to circuit components. The staff had concluded that the extension of the testing time interval from 18 months to each refueling interval was acceptable. The proposed change for testing from once each REFUELING INTERVAL to once per 24 months is acceptable because of the previous approval based on a testing frequency of 24 months.
SR 4.4.6.2.2 verifies operability of the reactor coolant system (RCS) pressure boundary isolation valves by verifying leakage to be within the limit. Ref. 9 gave the licensee approval to extend the testing time interval from 18 months to each refueling interval where the refueling interval would be 24 months. The approval was based on the review of records of maintenance and surveillance work. It was determined that the only preventative maintenance scheduled on an 18-month frequency for the motor-operated isolation valves involved visual inspection of the overall valve condition. It was also noted that in addition, the RCS leakage is continuously monitored by verifying RCS inventory at least once every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The proposed change for testing from once each REFUELING INTERVAL to once per 24 months is acceptable because of the previous approval based on a testing frequency of 24 months.
Because the staff had reviewed and approved the wording change for SR 4.4.4.1 and 3, 4.4.6.1, 4.4.6.2.2 and 4.4.9.3.1 in Amendment No. 133 from once each 18 months to once each REFUELING INTERVAL based on an evaluation where the surveillance frequency would be at least once per 24 months, this change is acceptable.
The licensee has also updated the Bases to incorporate the change from removing the undefined term REFUELING INTERVAL and recognizing that selected surveillances are completed once each 24 months and the staff has no objection to these changes.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Connecticut 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 surveillance requirements. 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 (67 FR 36930). 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 Commissions 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.
7.0 REFERENCES
- 1) J. F. Opeka letter to U.S. NRC, Millstone Unit No. 3, Proposed Revision to Technical Specifications - 24 Months Fuel Cycle, dated May 1, 1995.
- 2) Vernon L. Rooney letter to Robert E. Busch, Northeast Utilities Services Company,
Issuance of Amendment For 24-Month Fuel Cycle (TAC NO. M92203), dated December 28, 1995.
- 3) James W. Andersen letter to Neil S. Carns, Northeast Nuclear Energy Company, Millstone Nuclear Power Station, Unit 3 - Correction to Amendment No. 122 (TAC NO.
M92203)
- 4) Vernon L. Rooney letter to Robert E. Busch, Northeast Utilities Services Company,
Issuance of Amendment Month Fuel Cycle (B15263) (TAC NO. M93019), dated December 28, 1995
- 5) Vernon L. Rooney letter to Robert E. Busch, Northeast Utilities Services Company, Issuance of Amendment (TAC NO. M92591), dated February 5, 1996.
- 6) Vernon L. Rooney letter to Robert E. Busch, Northeast Utilities Services Company, Issuance of Amendment (TAC NO. M93020), dated December 28, 1995.
- 7) Vernon L. Rooney letter to John F. Opeka, Northeast Nuclear Energy Company, Issuance of Amendment (TAC NO. M91462), dated May 26, 1995.
- 8) Vernon L. Rooney letter to Ted C. Feigenbaum, Northeast Utilities Services Company, Issuance of Amendment (TAC NO. M92804), dated March 4, 1996.
- 9) James W. Andersen letter to Neil S. Carns, Northeast Nuclear Energy Company, Issuance of Amendment (TAC NO. M93018), dated February 19, 1997.
Principal Contributor: R. Pulsifer Date: July 24, 2002