ML030930318
| ML030930318 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 04/03/2003 |
| From: | Kalyanam N NRC/NRR/DLPM/LPD4 |
| To: | Venable J Entergy Operations |
| Kalyanam N, NRR/DLPM, 415-1480 | |
| Shared Package | |
| ML030930337 | List: |
| References | |
| TAC MB7150 | |
| Download: ML030930318 (15) | |
Text
April 3, 2003 Mr. Joseph E. Venable Vice President Operations Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - ISSUANCE OF AMENDMENT RE: CORRECTIONS AND CLARIFICATIONS TO VARIOUS TECHNICAL SPECIFICATION PAGES (TAC NO. MB7150)
Dear Mr. Venable:
The Commission has issued the enclosed Amendment No. 188 to Facility Operating License No. NPF-38 for the Waterford Steam Electric Station, Unit 3 (Waterford 3). The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated December 20, 2002.
The amendment makes several administrative changes to the Waterford 3 TSs, to revise, delete, correct, or clarify certain titles, page numbers, and heading information. The amendment also revises personnel and committee titles that have been changed, revises administrative reporting requirements to conform to 10 CFR 50.4, and deletes redundant or unnecessary requirements from TSs 5.4, 6.6, and 6.7.
A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice.
Sincerely,
/RA/
N. Kalyanam, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosures:
- 1. Amendment No. 188 to NPF-38
- 2. Safety Evaluation cc w/encls: See next page
- See previous concurrence NRR-058 OFFICE PDIV-1/PM PDIV-1/LA DSSA/SRXB
- DRIP/RORP
- PDIV-1/SC NAME NKalyanam DJohnson JWermiel RDennig RWeisman RGramm DATE 3/28/03 4/1/03 03/05/03 03/04/03 03/21/03 4/3/03 DOCUMENT NAME: G:\PDIV-1\Waterford\MB7150 - Amendment Package.wpd ENTERGY OPERATIONS, INC.
DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 188 License No. NPF-38
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Entergy Operations, Inc. (EOI) dated December 20, 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-38 is hereby amended to read as follows:
- 2. Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 188, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. EOI 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 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Robert A. Gramm, Chief, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 3, 2003
ATTACHMENT TO LICENSE AMENDMENT NO. 188 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 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 V V VI VI VII VII VIII VIII XI XI XII XII XIII XIII XIV XIV XV XV XVI XVI XVII XVII XVIII XVIII XIX XIX XX XX XXI XXI XXII XXII 2-1 2-1 3/4 3-4a 3/4 3-4a 3/4 3-17 3/4 3-17 3/4 3-18a 3/4 3-18a 3/4 4-32 3/4 4-32 3/4 7-16 3/4 7-16 3/4 7-18 3/4 7-18 3/4 7-18a 3/4 7-18a 3/4 7-18b 3/4 7-18b 3/4 7-18c 3/4 7-18c 3/4 8-7 3/4 8-7 3/4 11-18 ---------
5-5 5-5 5-6 5-6 6-2a 6-2a 6-5 6-5 6-6 6-6 6-8 6-8 6-13 ---------
6-14 6-14 6-17 6-17 6-18 6-18 6-20a 6-20a
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 188 TO FACILITY OPERATING LICENSE NO. NPF-38 ENTERGY OPERATIONS, INC.
WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382
1.0 INTRODUCTION
By application dated December 20, 2002, Entergy Operations, Inc. (the licensee), submitted a request for changes to the Waterford Steam Electric Station, Unit 3 (Waterford 3) Technical Specifications (TSs). The requested changes would make several administrative changes to the Waterford 3 TSs to revise, delete, correct, or clarify certain titles, page numbers, and heading information. The amendment would also revise personnel and committee titles that have been changed, revise administrative reporting requirements to conform to 10 CFR 50.4, and delete redundant or unnecessary requirements from TSs 5.4, 6.6, and 6.7.
2.0 REGULATORY EVALUATION
The regulations at 10 CFR 50.4 provide direction regarding written communications, and include address requirements, distribution requirements, form of communications, delivery of communications, and the regulation governing submission.
Pursuant to 10 CFR 50.36(c)(1) on Safety limits, limiting safety system settings, and limiting control settings, "... If any safety limit is exceeded, the reactor must be shut down. The licencee shall notify the Commission, review the matter, and record the results of the review ..."
and "For these reactors, the licensee shall notify the Commission as required by § 50.72 and submit a Licensee Event Report to the Commission as required by § 50.73..." The regulations at 10 CFR 50.36(c)(5) on administrative controls states "Administrative controls are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner. Each licensee shall submit any reports to the Commission pursuant to approved technical specifications as specified in § 50.4."
The regulations at 10 CFR 50.72 address the immediate notification requirements for operating nuclear power reactors for general events and non-emergency events under one-hour, four-hour, and eight-hour classifications. The licensee event report system is discussed in 10 CFR 50.73 .
The rest of the changes in the proposed amendment are administrative in nature and make editorial corrections; therefore, there are no specific regulatory requirements associated with the proposed amendment.
3.0 TECHNICAL EVALUATION
The changes requested by the licensee have been numbered as 3.1, 3.2, etc., and grouped as far as possible such that the review and resolution cover one or more changes.
3.1 INDEX page V: add "- Fxy" to PLANAR RADIAL PEAKING FACTORS title and "- Tq" to AZIMUTHAL POWER TILT title to match with titles on pages 3/4 2-3 and 3/4 2-4, respectively.
3.2 INDEX page VI: indent subsections under 3/4.4.1 to match format on page and add "SPRAY" to AUXILIARY title under 3/4.4.3 to match the title on page 3/4 4-9a, which was added in Amendment 22.
3.3 INDEX page VII: add "-W" to ELECTRIC HYDROGEN RECOMBINERS title to match the title on page 3/4 6-35.
3.4 INDEX page VIII: add identification for TS 3/4.7.6 CONTROL ROOM AIR CONDITIONING SYSTEM subsections: CONTROL ROOM EMERGENCY AIR FILTRATION SYSTEM - OPERATING, CONTROL ROOM EMERGENCY AIR FILTRATION SYSTEM - SHUTDOWN, CONTROL ROOM AIR TEMPERATURE -
OPERATING, CONTROL ROOM AIR TEMPERATURE - SHUTDOWN, and CONTROL ROOM ISOLATION AND PRESSURIZATION with corresponding page numbers. These index additions reflect changes made in Amendment 115. Also, indent 3/4.8.2 D.C. SOURCES to match page format.
3.5 INDEX page XI: add "- Fxy" to PLANAR RADIAL PEAKING FACTORS title to match title on page B 3/4 2-2, add "-Tq" to AZIMUTHAL POWER TILT title to match title on page B 3/4 2-2, correct page number for MONITORING INSTRUMENTATION from B 3/4 3-1 to B 3/4 3-2, and delete 3/4.3.4 TURBINE OVERSPEED PROTECTION reference as there is no place holder for this bases section, which was deleted in Amendment 103.
3.6 INDEX page XII: Revise page number for ECCS SUBSYSTEMS to read B 3/4 5-1b, revise page number for REFUELING WATER STORAGE POOL to read B 3/4 5-3, revise page number for CONTAINMENT ISOLATION VALVES to read B 3/4 6-5, revise page number for COMBUSTIBLE GAS CONTROL to read B 3/4 6-6, revise page number for VACUUM RELIEF VALVES to read B 3/4 6-6, revise page number for
SECONDARY CONTAINMENT to read B 3/4 6-7, and revise page number for STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION to read B 3/4 7-3d1.
3.7 INDEX page XIII: capitalize "and" to be consistent with the title for 3/4.7.3, COMPONENT COOLING WATER AND AUXILIARY COMPONENT COOLING WATER SYSTEMS and revise page number to read B 3/4 7-3d1, revise page number for FLOOD PROTECTION to read B 3/4 7-4a, revise page number for CONTROL ROOM AIR CONDITIONING SYSTEM to read B 3/4 7-4a, revise page number for CONTROLLED VENTILATION AREA SYSTEM to read B 3/4 7-4c, and revise page number for ESSENTIAL SERVICES CHILLED WATER SYSTEM to read B 3/4 7-7.
3.8 INDEX page XIV: delete "3/4.9.12 DELETED....B 3/4 9-3" as there is no place holder for this section, which was deleted in Amendment 176.
3.9 INDEX page XV: delete section 5.4 title REACTOR COOLANT SYSTEM and insert "NOT USED," and delete subsections 5.4.1 and 5.4.2 to agree with requested change to page 5-5 below. Add an "S" to LIMIT in the COMPONENT CYCLIC OR TRANSIENT LIMIT title to match the title on page 5-6.
3.10 INDEX page XVI: add "AND ONSITE ORGANIZATIONS" after OFFSITE in the title for SECTION 6.2.1 to match the title on page 6-1; delete titles, subtitles, and subtitle page numbers after Section 6.2.3 and insert "NOT USED" to agree with change made in Amendment 146; delete REVIEW AND AUDIT after Section 6.5 and replace with "NOT USED", and delete Section 6.5.1 in its entirety to agree with changes made in Amendment 109. These changes match the index with the cited TS page and previously approved changes.
3.11 INDEX page XVII: delete Section 6.5.2 in its entirety to agree with changes made in Amendment 109; delete Section 6.6 title REPORTABLE EVENT ACTION and page number, and insert "NOT USED" to agree with changes proposed in this amendment; delete Section 6.7 title SAFETY LIMIT VIOLATION and page number, and insert "NOT USED" to agree with changes proposed in this amendment; revise page number for REPORTING REQUIREMENTS to read 6-17; revise page number for ROUTINE REPORTS to read 6-17; insert "COLR" after CORE OPERATING LIMITS REPORT; and 1
In the TS markup pages submitted by the licensee, index page XII provides the page number for Section 3/4.7.2 - STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION as B 3/4 7-3b and index page XIII provides the page number for Section 3/4.7.3 -
COMPONENT COOLING WATER AND AUXILIARY COMPONENT COOLING WATER SYSTEMS as B 3/4 7-3b. However, Bases Change No. 15 added two new sections, under the headings "Credited Non-Safety Related Support Systems for MFIV [Main Feedwater Isolation Valve] Operability" and "RTO [Reactor Trip Override] and AFW [Auxiliary Feedwater] Pump HDPT [High Discharge Pressure Trip] Test Requirements" which caused the page numbers for Section 3/4.7.2 and Section 3/4.7.3 to change to B 3/4 7-3d. The staff finds the discrepancy minor and therefore acceptable.
delete Section 6.10 title RECORD RETENTION and page number, and insert "NOT USED" to agree with changes made in Amendment 146.
3.12 INDEX page XVIII: add "(PCP)" after PROCESS CONTROL PROGRAM and "(ODCM)"
after OFFSITE DOSE CALCULATION MANUAL to match titles on pages 6-23 and 6-24, respectively.
3.13 INDEX page XIX: change Figure 3.4-2 and Figure 3.4-3 titles to delete PRESSURE/TEMPERATURE LIMITATIONS FOR 0-8 EFFECTIVE FULL POWER YEARS and insert "PRESSURE-TEMPERATURE LIMITS 0-16 EFPY" after REACTOR COOLANT SYSTEM to match titles of corresponding figures on pages 3/4 4-30 and 4-31 that were revised in Amendment 160; add Figure "3.6-1 DELETED...3/4 6-12" to reflect the place holder for the figure that was deleted in Amendment 27; insert titles for Figures 5.6-1, 5.6-2, and 5.6-3 with respective page numbers after FIGURE 5.1-3 to reflect the figures added by Amendment 144; and in FIGURES 6.2-1 and 6.2-2 replace the titles with words "DELETED" to reflect the place holders for the tables deleted by Amendment 41.
3.14 INDEX page XX: delete Table 2.2-2 title and page number to reflect the disposition of the table, which was deleted in Amendment 5.
3.15 INDEX page XXI: delete Table 3.3-12 and 4.3-8, the words "DELETED", and associated page numbers as there are no longer any place holders for these tables, which were deleted in Amendment 68.
3.16 INDEX page XXII: add "PER TRAIN" after ULTIMATE HEAT SINK MINIMUM FAN REQUIREMENTS, insert Table "4.7-2 SNUBBER VISUAL INSPECTION INTERVAL...3/4 7-21a" after Table 3.7-3 to reflect the table added by Amendment 73, and delete information related to Tables 4.8-1 and 4.8-1a which were deleted per Amendment 126.
The changes described in 3.1 through 3.16 are changes made to the INDEX pages, to agree with the text in the respective sections which were either previously approved by various amendment requests or are changes that are detailed in this request. These are corrections, clarifications, and/or updates to the INDEX pages and do not change the technical content, intent, or interpretation of the TS and, therefore, the staff finds these changes to be acceptable.
3.17 Page 2-1: delete ", and comply with the requirements of Specification 6.7.1" in four ACTION statements.
TS 6.7.1 contains actions to be taken in the event of a Safety Limit Violation. These actions require that the NRC Operations Center be notified by telephone as soon as possible and in all cases within one hour, and the Vice President of Operations and the Safety Review Committee (SRC) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following any such violation. Further, a report describing applicable circumstances preceding the violation; effects of the violation on the facility components, systems, or structure; and corrective action taken to prevent recurrence of the violation must be submitted to the Commission, SRC, and the Vice President of Operations within 14 days of the
violation. TS 6.7.1 also requires that critical operation of the unit not be resumed until authorized by the Commission.
The licensee states that these requirements are after-the-fact notifications and reviews, and are not required to assure the safe operation of the facility. These requirements are duplicated in 10 CFR 50.36, 10 CFR 50.72, and 10 CFR 50.73, except the telephone notification to the NRC Operations Center may be made within four hours, as set forth in 10 CFR 50.72(b)(2),
LERs under 10 CFR 50.73 may be submitted within sixty days. Because Waterford 3 is still required to meet these regulations, repetition of the requirements in the TSs is not needed.
Additionally, these changes are consistent with NUREG-1432, Revision 2, as modified by TSTF-5, Revision 1. The removal of the statements from TS Safety Limit Action 2.1.1.1, Safety Limit Action 2.1.1.2, and Safety Limit Action 2.1.2, and conforming change made to page 2-1, are administrative changes, do not change the technical content, intent, or interpretation of these of the TS and do not relieve the licensee of any obligations except to extend reporting time to that which is specified in the regulations. Therefore, the staff finds these changes to be acceptable.
3.18 Page 3/4 3-4a: ACTION 2 change Plant Operations Review Committee to "On-Site Safety Review Committee" to reflect correct title.
3.19 Page 3/4 3-17: ACTION 13 change Plant Operations Review to "On-Site Safety Review" to reflect correct title.
3.20 Page 3/4 3-18a: ACTION 19a change Plant Operations to "On-Site Safety" to reflect correct title.
The licensee states that these revisions correct obsolete position or committee titles and the changes are as a result of internal efforts to standardize certain position or committee titles within the licensee organization. The staff considers the changes to be editorial in nature, and finds them to be acceptable.
3.21 Page 3/4 4-32: delete information on this page and insert "THIS PAGE NOT USED" for consistent format; also, rotate the page from landscape to portrait format.
The staff considers the change to be editorial in nature, and finds it to be acceptable.
3.22 Page 3/4 7-16: change title after "PLANT SYSTEMS" to read "3/4 7.6 CONTROL ROOM AIR CONDITIONING SYSTEM" and add "CONTROL ROOM EMERGENCY AIR FILTRATION SYSTEM - OPERATING" before LIMITING CONDITION FOR OPERATION to better conform to the TS format.
3.23 Page 3/4 7-18: delete "3/4.7.6.2" above LIMITING CONDITION FOR OPERATION and change title to read "CONTROL ROOM EMERGENCY AIR FILTRATION SYSTEM -
SHUTDOWN" to better conform to the TS format.
3.24 Page 3/4 7-18a: delete "3/4.7.6.3" above LIMITING CONDITION FOR OPERATION and change title to read "CONTROL ROOM AIR TEMPERATURE - OPERATING" to better conform to the TS format.
3.25 Page 3/4 7-18b: delete "3/4.7.6.4" above LIMITING CONDITION FOR OPERATION and change title to read "CONTROL ROOM AIR TEMPERATURE - SHUTDOWN" to better conform to the TS format.
3.26 Page 3/4 7-18c: delete "3/4.7.6.5" above LIMITING CONDITION FOR OPERATION to better conform to the TS format.
3.27 Page 3/4 8-7: delete information on this page and insert "THIS PAGE NOT USED" for consistent format.
3.28 Page 3/4 11-18: delete page in its entirety as it is at the end of the section and is not needed as a place holder.
The staff considers these changes to be editorial in nature and therefore acceptable.
3.29 Page 5.5: delete Section 5.4 title REACTOR COOLANT SYSTEM and insert "NOT USED;" delete Section 5.4.1 DESIGN PRESSURE AND TEMPERATURE and Section 5.4.2 VOLUME in their entirety to conform to NUREG-1432, Revision 2, "Standard Technical Specifications - Combustion Engineering Plants" which no longer includes this information in the DESIGN FEATURES section.
The licensee states that the Reactor Coolant System (RCS) volume contained in TS 5.4.2 is consistent with the nominal design value listed in the Final Safety Analysis Report (FSAR)
Table 5.1-2 and Table 5.1-3, and the other references throughout the FSAR are correct. Prior to Thot reduction change, approved in Amendment 120, FSAR Table 5.1-2 listed the average operating temperature, Tavg as 582.1 oF, which matches with the value in TS 5.4.2. However, following the Thot reduction change, this number was revised to 574 oF in the FSAR table but not in the TS. The temperature in TS 5.4.2 is a nominal temperature at which the RCS volume was originally calculated. The approximately 8 oF change has a negligible effect on the RCS volume. Since the nominal temperature is not a controlling temperature for plant operation, the current nominal value of Tavg was determined to be adequate until such time as the TS was amended to delete TS 5.4. The deletion of these sections is consistent with NUREG-1432, Revision 2 and 10 CFR 50.36(c)(4).
The staff agrees with the changes proposed by the licensee and finds the changes acceptable.
3.30 Page 5.6: correct spelling of refuelling to "refueling" in Section 5.6.1.c and correct spelling of accceptable to "acceptable" in Section 5.6.1.f.
The proposed changes correct existing spelling errors and the staff finds them acceptable.
3.31 Page 6-2a ADMINISTRATIVE CONTROLS paragraph f.: change Operations Superintendent to "Assistant Operations Manager (Shift)" to reflect correct title.
The proposed change involves correction to the title. While in the markup of the TS pages in the application dated December 20, 2002, the change is shown as "Assistant Operations Manager (shift)", the clean copy of the TS page has the letter "s" in "shift" capitalized. The staff considers this change, including the change between the mark-up and clean TS pages,
editorial, not significant to safety, and does not alter any technical requirements. The staff finds the proposed change acceptable.
3.32 Page 6.5 TABLE 6.2-1: change Superintendent to "Manager" (four places) and the acronym SS to "SM" (three places) to correct titles.
3.33 Page 6-6 Section 6.2.4.1: change Superintendent to "Manager" to correct title.
The proposed changes involve corrections to titles and do not alter any technical requirements, intent of these specifications, or interpretation of these specifications. Therefore, the NRC staff finds the proposed changes acceptable.
3.34 Page 6.8: change 6-12 to read "6-13" in the middle of the page and 6-13 to "6-14" at the bottom of the page to reflect the deletion of page 6-13 as proposed in the next item below.
3.35 Page 6-13 and 6-14: delete TSs 6.6 and 6.7, and delete page 6-13 in its entirety.
TS 6.6.1 discusses the actions taken for REPORTABLE EVENTS (LERs) and as set forth in 10 CFR 50.73. Because Waterford 3 is still required to meet this regulation, repetition of the regulatory requirements in the TS is not needed. Also, in view of the explanation provided for 3.17, the staff finds the changes in 3.34 and 3.35 acceptable.
3.36 Page 6-14: insert "6.6 NOT USED" and "6.7 NOT USED" above 6.8 and change PORC in NOTES: (1) to "On-Site Safety Review Committee".
TSs 6.6 and 6.7 were deleted in 3.35, and 3.36 clarifies the deletion by the explanation "6.6 NOT USED" and "6.7 NOT USED." The staff accepts this change. Changing PORC to "On-Site Safety Review Committee" in NOTES: (1) involves correction to a title and does not alter any technical requirements, intent of these specifications, or interpretation of these specifications. Therefore, the NRC staff finds the proposed change acceptable.
3.37 Page 6-17: revise TS 6.9.1 to read, "The following reports shall be submitted in accordance with 10 CFR 50.4."
3.38 Page 6-18: revise TS 6.9.1.6 by deleting "to the Director, Office of Resource Management, U. S. Nuclear Regulatory Commission, Washington, DC 20555, with a copy to the Regional Administrator of the regional office of the NRC."
3.39 Page 6-20a: revise TS 6.9.2 to read "Special Reports shall be submitted in accordance with 10 CFR 50.4 within the time period specified for each report."
On November 6, 1986, the NRC amended its regulation (51 FR 40303) to establish procedures for submitting correspondence, reports, applications, or other written communications pertaining to the domestic licensing of production and utilization facilities. The rule superseded all existing requirements and guidance with respect to the number of copies and mailing procedures. Licensees whose TSs contained conflicting submittal directions were authorized by the rule to delete conflicting directions by pen-and-ink changes to their TSs. The Commission did not require formal applications for amendments to effect these changes. The
changes proposed to TS 6.9.1, TS 6.9.1.6, and TS 6.9.2 formally conform the current Waterford 3 TSs to this rule change by deleting superceded information and directing that the reports be submitted in accordance with 10 CFR 50.4 within the time period specified for each report. The staff finds this change to be acceptable.
3.40 The licensee also provided changes to the TS Bases pages B 3/4 2-2, B 3/4 3-3, B 3/4 7-4a, and B 3/4 7-5 for information.
Since the changes are related to Bases changes and are provided to the NRC for information only, the new Bases page will be prepared using the marked-up page in Attachment 3 under 50.59 once the overall change is approved by the NRC. The staff finds this approach acceptable.
4.0
SUMMARY
The NRC staff reviewed the proposed changes to TS 3.1 through 3.39, discussed above. The proposed changes do not alter any technical requirements, intent of these specifications, or interpretation of these specifications. Therefore, the NRC staff finds the proposed changes acceptable.
5.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Louisiana State official was notified of the proposed issuance of the amendment. The State official had no comments.
6.0 ENVIRONMENTAL CONSIDERATION
The amendment changes record keeping, reporting, or administrative procedures or 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 (68 FR 5673 dated February 4, 2003). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). 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.
7.0 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.
Principal Contributor: N. Kalyanam Date: April 3, 2003
Waterford Generating Station 3 cc:
Mr. Michael E. Henry, Administrator Regional Administrator, Region IV and State Liaison Officer U.S. Nuclear Regulatory Commission Department of Environmental Quality 611 Ryan Plaza Drive, Suite 1000 P.O. Box 82135 Arlington, TX 76011 Baton Rouge, LA 70884-2135 Parish President Council Vice President, Operations Support St. Charles Parish Entergy Operations, Inc. P.O. Box 302 P.O. Box 31995 Hahnville, LA 70057 Jackson, MS 39286-1995 Executive Vice President Director & Chief Operating Officer Nuclear Safety Assurance Entergy Operations, Inc.
Entergy Operations, Inc. P. O. Box 31995 17265 River Road Jackson, MS 39286-1995 Killona, LA 70066-0751 Chairman Wise, Carter, Child & Caraway Louisiana Public Services Commission P. O. Box 651 P.O. Box 91154 Jackson, MS 39205 Baton Rouge, LA 70825-1697 General Manager Plant Operations Waterford 3 SES Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751 Licensing Manager Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751 Winston & Strawn 1400 L Street, N.W.
Washington, DC 20005-3502 Resident Inspector/Waterford NPS P.O. Box 822 Killona, LA 70066-0751