ML020090379
| ML020090379 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 04/25/2002 |
| From: | Milano P NRC/NRR/DLPM/LPD1 |
| To: | Kansler M Entergy Nuclear Operations |
| Milano, P , NRR/DLPM, 415-1457 | |
| References | |
| TAC MB2947 | |
| Download: ML020090379 (13) | |
Text
April 25, 2002 Mr. Michael Kansler Senior Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 - ISSUANCE OF AMENDMENT TO REVISE THE POST ACCIDENT MONITORING INSTRUMENTATION TECHNICAL SPECIFICATIONS (TAC NO. MB2947)
Dear Mr. Kansler:
The Commission has issued the enclosed Amendment No. 211 to Facility Operating License No. DPR-64 for the Indian Point Nuclear Generating Unit No. 3. The amendment consists of changes to the Technical Specifications (TSs) in response to your application transmitted by letter dated September 7, 2001, as revised December 17, 2001.
The amendment revises the Post Accident Monitoring Instrumentation Technical Specifications to ensure that licensee commitments to Regulatory Guide 1.97 are properly reflected.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commissions next regular biweekly Federal Register notice.
Sincerely,
/RA/
Patrick D. Milano, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-286
Enclosures:
- 1. Amendment No. 211 to DPR-64
- 2. Safety Evaluation cc w/encls: See next page
April 25, 2002 Mr. Michael Kansler Senior Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 - ISSUANCE OF AMENDMENT TO REVISE THE POST ACCIDENT MONITORING INSTRUMENTATION TECHNICAL SPECIFICATIONS (TAC NO. MB2947)
Dear Mr. Kansler:
The Commission has issued the enclosed Amendment No. 211 to Facility Operating License No. DPR-64 for the Indian Point Nuclear Generating Unit No. 3. The amendment consists of changes to the Technical Specifications (TS) in response to your application transmitted by letter dated September 7, 2001, as revised December 17, 2001.
The amendment revises the Post Accident Monitoring Instrumentation Technical Specifications to ensure that licensee commitments to Regulatory Guide 1.97 are properly reflected.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commissions next regular biweekly Federal Register notice.
Sincerely,
/RA/
Patrick D. Milano, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-286
Enclosures:
- 1. Amendment No. 211 to DPR-64
- 2. Safety Evaluation cc w/encls: See next page Accession Number: ML020090379 *Safety Evaluation provided 12/26/2001 and no major changes were made OFFICE PDI-1\PM PDI-1\LA OGC PDI-1\SC EEIB:DE\SC
- NAME PMilano SLittle AHodgdon RLaufer EMarinos DATE 04/10/02 04/10/02 04/15/02 04/22/02 12/26/01 Official Record Copy
DATED: April 25, 2002 AMENDMENT NO. 211 TO FACILITY OPERATING LICENSE NO. DPR-64 INDIAN POINT UNIT 3 PUBLIC PDI R/F RLaufer SLittle PMilano OGC GHill (2)
WBeckner BMarcus ACRS BPlatchek, RI cc: Plant Service list
Indian Point Nuclear Generating Unit No. 3 cc:
Mr. Jerry Yelverton Mr. Harry P. Salmon, Jr.
Chief Executive Officer Director of Oversight Entergy Operations Entergy Nuclear Operations, Inc.
1340 Echelon Parkway 440 Hamilton Avenue Jackson, MS 39213 White Plains, NY 10601 Mr. Robert J. Barrett Mr. James Comiotes Vice President - Operations Director, Nuclear Safety Assurance Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.
Indian Point Nuclear Generating Unit 3 Indian Point Nuclear Generating Unit 3 295 Broadway, Suite 3 295 Broadway, Suite 3 P. O. Box 308 P.O. Box 308 Buchanan, NY 10511-0308 Buchanan, NY 10511-0308 Mr. Dan Pace Mr. John Donnelly Vice President Engineering Licensing Manager Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.
440 Hamilton Avenue Indian Point Nuclear Generating Unit 3 White Plains, NY 10601 295 Broadway, Suite 3 P.O. Box 308 Mr. James Knubel Buchanan, NY 10511-0308 Vice President Operations Support Entergy Nuclear Operations, Inc. Mr. John McCann 440 Hamilton Avenue Manager, Licensing and Regulatory Affairs White Plains, NY 10601 Entergy Nuclear Operations, Inc.
Indian Point Nuclear Generating Unit 2 Mr. Joseph DeRoy 295 Broadway, Suite 1 General Manager Operations P. O. Box 249 Entergy Nuclear Operations, Inc. Buchanan, NY 10511-0249 Indian Point Nuclear Generating Unit 3 295 Broadway, Suite 3 Resident Inspectors Office P. O. Box 308 U.S. Nuclear Regulatory Commission Buchanan, NY 10511-0308 295 Broadway, Suite 3 P.O. Box 337 Mr. John Kelly Buchanan, NY 10511-0337 Director - Licensing Entergy Nuclear Operations, Inc. Regional Administrator, Region I 440 Hamilton Avenue U.S. Nuclear Regulatory Commission White Plains, NY 10601 475 Allendale Road King of Prussia, PA 19406 Ms. Charlene Fiason Licensing Mr. John M. Fulton Entergy Nuclear Operations, Inc. Assistant General Counsel 440 Hamilton Avenue Entergy Nuclear Operations, Inc.
White Plains, NY 10601 440 Hamilton Avenue White Plains, NY 10601
Indian Point Nuclear Generating Unit No. 3 cc:
Ms. Stacey Lousteau Mr. Ronald Schwartz Treasury Department SRC Consultant Entergy Services, Inc. 64 Walnut Drive 639 Loyola Avenue Spring Lake Heights, NJ 07762 Mail Stop: L-ENT-15E New Orleans, LA 70113 Mr. Ronald J. Toole SRC Consultant Mr. William M. Flynn, President Toole Insight New York State Energy, Research, and 605 West Horner Street Development Authority Ebensburg, PA 15931 Corporate Plaza West 286 Washington Avenue Extension Mr. Charles W. Hehl Albany, NY 12203-6399 SRC Consultant Charles Hehl, Inc.
Mr. J. Spath, Program Director 1486 Matthew Lane New York State Energy, Research, and Pottstown, PA 19465 Development Authority Corporate Plaza West Mr. Alex Matthiessen 286 Washington Avenue Extension Executive Director Albany, NY 12203-6399 Riverkeeper, Inc.
25 Wing & Wing Mr. Paul Eddy Garrison, NY 10524 Electric Division New York State Department Mr. Paul Leventhal of Public Service The Nuclear Control Institute 3 Empire State Plaza, 10th Floor 1000 Connecticut Avenue NW Albany, NY 12223 Suite 410 Washington, DC, 20036 Mr. Charles Donaldson, Esquire Assistant Attorney General Mr. Karl Copeland New York Department of Law Pace Environmental Litigation Clinic 120 Broadway 78 No. Broadway New York, NY 10271 White Plains, NY 10603 Mayor, Village of Buchanan Jim Riccio 236 Tate Avenue Greenpeace Buchanan, NY 10511 702 H Street, NW Suite 300 Mr. Ray Albanese Washington, DC 20001 Executive Chair Four County Nuclear Safety Committee Westchester County Fire Training Center 4 Dana Road Valhalla, NY 10592
ENTERGY NUCLEAR OPERATIONS, INC.
DOCKET NO. 50-286 INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 211 License No. DPR-64
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Entergy Nucleaar Operations, Inc. (the licensee) dated September 7, 2001, as revised December 17, 2001, 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. DPR-64 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 211, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Richard J. Laufer, Chief,Section I Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 25, 2002
ATTACHMENT TO LICENSE AMENDMENT NO. 211 FACILITY OPERATING LICENSE NO. DPR-64 DOCKET NO. 50-286 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 Pages Insert Pages 3.3.3-1 3.3.3-1 3.3.3-2 3.3.3-2 3.3.3-4 3.3.3-4 3.3.3-5 3.3.3-5
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 211 TO FACILITY OPERATING LICENSE NO. DPR-64 ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286
1.0 INTRODUCTION
By letter dated September 7, 2001, as revised by letter dated December 17, 2001, Entergy Nuclear Operations, Inc. (the licensee) submitted a request for changes to the Indian Point Nuclear Generating Unit No. 3 (IP3) Technical Specifications (TSs). The requested changes would revise the Post Accident Monitoring (PAM) Instrumentation TSs to ensure that licensee commitments to Regulatory Guide 1.97 are properly reflected. The December 17, 2001, letter provided a revised no significant hazards consideration determination and further revisions to the TSs.
2.0 EVALUATION The licensee has requested changes to the PAM TS for: a) Core Exit Thermocouples (CETs),
b) Steam Generator (SG) Water Level (Wide Range), c) Auxiliary Feedwater Flow, d) Reactor Coolant System (RCS) Hot Leg Temperature (Thot), e) RCS Cold Leg Temperature (Tcold), and f)
Main Steam Line Radiation.
The design of the PAM instrumentation is that SG Water Level (Wide Range), Auxiliary Feedwater Flow, Thot, Tcold, and Main Steam Line Radiation have one channel of instrumentation per loop, SG, or steam line. Each of these functions has alternate instrumentation designated as a diverse channel.
For all of the PAM Functions entry into Condition A is "One or more Functions with one required channel inoperable" and entry into Condition C is "One or more Functions with two required channels inoperable." Separate condition entry is allowed for each function.
a) There are ten qualified CETs in each of two trains with a minimum of two CETs per channel in each of the four core quadrants. The location of the CETs is such that an evaluation can be made of core radial decay heat distribution. Table 3.3.3-1 includes a separate CET Function for each quadrant (Functions 18, 19, 20, and 21).
The licensee has proposed to change the names of Functions 18, 19, 20, and 21 from "Core Exit Thermocouples..." to "Core Exit Temperature...". These name changes adopt the wording in NUREG-1431, Revision 2, "Standard Technical Specifications Westinghouse Plants" (STS) and are editorial in nature.
The licensee has proposed to change the Required Channels for each Core Exit Temperature Function from "2 per train" to "2" with a note that reads, "A channel consists of two core exit thermocouples (CETs)."
The existing wording "2 per train" could be interpreted to mean two channels per train and since there are two trains, this would imply that four channels are required. This would result in a requirement that is unintentionally more restrictive than the STS and not consistent with the design of the plant, which has two trains, which are intended to be the required two channels.
The proposed wording follows the wording in the STS and correctly reflects the design of the plant and the number of channels required.
b & c) There is one SG Water Level (Wide Range) channel in each SG and one Auxiliary Feedwater Flow channel in each SG. SG Water Level (Wide Range) and Auxiliary Feedwater Flow in the same SG are diverse channels to each other.
The required number of channels for the SG Water Level (Wide Range) Function (Function 14) is one channel per SG of SG Water Level (Wide Range) and one channel per SG of Auxiliary Feedwater Flow for the same SG. The required number of channels for the Auxiliary Feedwater Flow Function (Function 15) is one channel of Auxiliary Feedwater Flow for each SG and one channel of SG Water Level (Wide Range) for the same SG.
However, the note that specifies Auxiliary Feedwater Flow as the diverse channel for SG Water Level (Wide Range) (note f) which reads, "The redundant channel in each steam generator is the auxiliary feedwater flow rate channel for that steam generator,"
does not also specify that SG Water Level (Wide Range) is the diverse channel for Auxiliary Feedwater Flow. Additionally, this note is not referenced by the Auxiliary Feedwater Flow Function.
The use of notes to provide information about diverse channels is an unnecessarily complex method of providing this information in the TSs. Therefore, the licensee has proposed to include both SG Water Level (Wide Range) and Auxiliary Feedwater Flow in the same function (Function 14) and delete note f. The Function would be structured as "SG Water Level (Wide Range) and Auxiliary Feedwater Flow" with the Required Channels as "1 each per SG." This would allow the use of standard Condition entry statements. Function 15 would not be used, to avoid having to renumber other functions in Table 3.3.3-1.
The SR 3.3.3.2 surveillance frequency is 24 months for SG Water Level (Wide Range) and 18 months for Auxiliary Feedwater Flow. The licensee has proposed an editorial change to Table 3.3.3-1 to insure that these surveillance frequencies are properly indicated in the combined Function 14.
The proposed wording follows the wording in the STS and the TS of other plants with single channels of instrumentation and correctly reflects the design of the plant and number of channels required.
d) There is one channel of Thot per loop. The diverse channel for Thot in each loop is any qualified Core Exit Temperature channel in the quadrant associated with that loop.
There are a minimum of two Core Exit Temperature channels per quadrant. The required number of channels for the Thot Function (Function 2) is one channel per loop of Thot and any qualified Core Exit Temperature channel in the quadrant associated with that loop.
However, the note that specifies the diverse channel for Thot as any qualified CET in the quadrant associated with that loop (note a) which reads, "The redundant channel in each of four loops is any qualified CET in the quadrant associated with that loop," is incorrect. The diverse channel is "any qualified Core Exit Temperature channel" not "any qualified CET."
The use of notes to provide information about diverse channels is an unnecessarily complex method of providing this information in the TSs. Therefore, the licensee has proposed to include this information in the Condition entry statements and delete note a.
The proposed revision to the Condition C entry statement would add "OR One required Thot channel and two required Core Exit Temperature channels inoperable."
The proposed wording follows the wording in the STS and the TS of other plants with single channels of instrumentation and correctly reflects the design of the plant and number of channels required.
The licensee has also proposed to change the name of Function 2 from "RCS Hot Leg Temperature (Wide Range)" to "RCS Hot Leg Temperature (Wide Range) (Thot)." This change in name is editorial in nature and provides consistency throughout TS 3.3.3.
e) There is one channel of Tcold per loop. The diverse channel for Tcold in each loop is any channel of SG Pressure in the associated SG. There are three channels of SG Pressure in each SG. The required number of channels for the Tcold Function (Function
Note b specifies the diverse channel for Tcold as SG Pressure. It reads, "The redundant channel in each of four loops is any channel of steam generator pressure for that loop."
The use of notes to provide information about diverse channels is an unnecessarily complex method of providing this information in the TSs. Therefore, the licensee has proposed to include this information in the Condition entry statements and delete note b.
The proposed revision to the Condition C entry statement would add "OR One required Tcold channel and two required SG Pressure channels inoperable."
The proposed wording follows the wording in the STS and the TS of other plants with single channels of instrumentation and correctly reflects the design of the plant and number of channels required.
The licensee has also proposed to change the name of Function 3 from "RCS Cold Leg Temperature (Wide Range)" to "RCS Cold Leg Temperature (Wide Range) (Tcold)," and change the name of Function 16 from "Steam Generator Pressure" to "SG Pressure."
These name changes are editorial in nature and are duplicated throughout TS 3.3.3.
f) There is one channel of Main Steam Line Radiation per steam line. The diverse channel for Main Steam Line Radiation in each steam line is any SG Water Level (Narrow Range) channel in the associated SG. There are three channels of SG Water Level (Narrow Range) in each SG. The required number of channels for the Main Steam Line Radiation Function (Function 22) is one channel per steam line of Main Steam Line Radiation and one channel per SG of SG Water Level (Narrow Range) for the associated SG.
However the note that specifies SG Water Level (Narrow Range) as the diverse channel for Main Steam Line Radiation (note g), which reads, "The redundant channel in each steam line is any one steam generator narrow range level indicator for that loop," is not referenced by the Main Steam Line Radiation Function.
The use of notes to provide information about diverse channels is an unnecessarily complex method of providing this information in the TS. Therefore, the licensee has proposed to include this information in the Condition entry statements and delete note g.
The proposed revision to the Condition C entry statement would add "OR One required Main Steam Line Radiation channel and two required SG Water Level (Narrow Range) channels inoperable."
The proposed wording follows the wording in the STS and the TS of other plants with single channels of instrumentation and correctly reflects the design of the plant and number of channels required.
The deletion of notes (a), (b), and (f) require the renumbering of the remaining notes. Note (c) becomes note (a), note (d) becomes note (b), and note (e) becomes note (c). The new note added for Core Exit Temperature becomes note (d). The change of the note names is editorial in nature.
Based on the above review and the licensees justification for IP3 TS changes, the NRC staff concludes that the proposed revision of TS 3.3.3 is consistent with NRC regulations, the guidelines in Chapter 7 of the Standard Review Plan, and the STS. The staff, therefore, finds the proposed TS changes acceptable.
3.0 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.
4.0 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. 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 5328). 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.
5.0 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: B. Marcus Date: April 25, 2002