B15306, Application for Amend to License NPF-49,revising TS Re Nominal 24 Month Fuel Cycle Surveillance Extensions for Millstone Unit 3

Application for Amend to License NPF-49,revising TS Re Nominal 24 Month Fuel Cycle Surveillance Extensions for Millstone Unit 3

ML20086S117
Person / Time
Site:	Millstone
Issue date:	07/26/1995
From:	Opeka J NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES SERVICE CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20086S119	List: B15306, Application for Amend to License NPF-49,revising TS Re Nominal 24 Month Fuel Cycle Surveillance Extensions for Millstone Unit 3 ML20086S127
References
B15306, NUDOCS 9508010102
Download: ML20086S117 (8)

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2 P.O. Box 270 llartford, CT 06141-0270 (203) 665-5000 July 26, 1995 Docket No. 50-423 B15306 Re: 10CFR50.90 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specifications 24-Month Fuel Cycle - Instrumentation Surveillance Extensions Introduction Pursuant to 10CFR50.90, Northeast Nuclear Energy Company (NNECO) hereby proposes to amend its Operating License, NPF-49, by incorporating the attached proposed changes into the Millstone i Unit No. 3 Technical Specifications.  !

Discussion On June 7, 1995, Millstone Unit No. 3 began operating on a nominal 24-month fuel cycle instead of the previous 18-month fuel cycle. The amendment request included in this letter represents the last in a series of submittals necessary to support the nominal 24-month fuel cycle surveillance extensions for Millstone Unit No. 3. Attachment 1 lists all other submittals transmitted to the NRC for review and approval to date. These submittals support the nominal 24-month fuel cycle surveillance extensions for Millstone Unit No. 3.

l. This submittal is considered a cost beneficial licensing action l

by NNECO. Implementation of a 24-month fuel cycle would save in excess of the $100,000 guideline identified by the NRC Staff with no reduction in public health and safety.

This submittal modifies the frequency of several surveillance requirements of the Millstone Unit No. 3 Technical Specifications. These surveillanco requirements pertain to:

Reactor Trip System Instrumentation ESFAS Ir..itrumentation l

Remote Shutdown Instrumentation Accident Monitoring Instrumentation '

RCS Total Flow Rate

- Process and Radiation Monitoring Instrumentation

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U. S. Nuclear Regulatory Commission B15306/Page 2 July 26, 1995 In support of this license amendment request, the following information is provided:

• Attachment 2 and Attachment 3 forward the c:rked-up and retyped technical specification pages, and reflect the currently issued version of the technical specifications.

• Attachment 4 describes the proposed technical specification changes.

• Attachment 5 provides a safety assessment for the changes.

NNECO has reviewed the proposed technical specification changes in accordance with 10CFR50.92 and has determined that the changes do not involve a significant hazards consideration (SHC). The information concerning the

setpoint methodology for the reactor protection system /

engineered safety features actuation systems will be submitted under a separate cover because the information is proprietary to Westinghouse Electric Corporation.

Moreover, the Commission has provided guidance concerning the application of standards in 10CFR50.92 by providing certain examples (March 6, 1986, 51 FR 7751) of amendments that are considered not likely to involve an SHC. The proposed changes described in Attachment 4 are not enveloped by a specific

. example. However, it has been demonstrated (i.e. , Attachment 5) that the proposed changes do not involve an SHC. Therefore, the j proposed changes do not negatively impact the public health or j safety.

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Environmental Consideration NNECO htts reviewed the proposed license amendment against the criteria of 10CFR51.22 for environmental considerations. The proposed changes do not involve an SHC, do not significantly increase the types and amounts of effluents that may be released off site, nor significantly increase individual or cumulative occupational radiation exposures. Based on the foregoing, NNECO concludes that the proposed changes meet the criteria delineated in 10CFR51.22 (c) (9) for a categorical exclusion from the requirement of an environmental impact statement.

Nuclear Safety Assessment Board Review The Nuclear Safety Assessment Board has reviewed this proposed amendment request and concurs with the above determination.

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U. S. Nuclear Regulatory Commission B15306/Page 3 July 26, 1995 State Notification In accordance with 10CFR50.91(b) , we are providing the State cf Connecticut with a copy of this proposed amendment request to ensure their awareness of this request.

Schedule Required for NRC Approval As stated earlier, this submittal represents the last in a series of license amendment requests necessary to support the conversion to a nominal 24-month fuel cycle at Millstone Unit No. 3 On June 7, 1995, Millstone Unit No. 3 began operating on a nominal 24-month fuel cycle instead of the previous 18-month fuel cycle. t It is our objective to obtain NRC approval of all the amendment  ?

requests related to the 24-month fuel cycle by September 1996.

NNECO requests that the license amendment be effective upon issuance with implementation within 90 days.

Commitment The following is NNECO's commitment made within this letter.

Other statements within this letter are provided as information only. i B15306-1 NNECO will submit a license amendment request to reflect the installation of the new transmitters for certain Reactor Trip and Engineered Safety Function Actuation System Instrumentation to support Cycle 7 operation.

If the NRC Staff should have any questions or comments regarding this submittal, please contact Mr. F.. G. Joshi at (203) 440-2080.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY 4 -

J. F. Okeky e ')/

Executive Vice Prehldent cc: See Page 4

U. S. Nuclear Regulatory Commission B15306/Page'4 July 26, 1995 cc: T. T. Martin, Region I Administrator l

V. L. Rooney, NRC Project Manager, Millstone Unit No. 3 P. D. Swetland, Senior Resident Inspector, Millstone Unit Nos. 1, 2, and 3 Mr. Kevin T.A. McCarthy, Director Monitoring and Radiation Division Department of Environmental Protection 79 Elm Street P.O. Box 5066 Hartford, CT 06102-5066 Subscribed and sworn to before me this 26'M day of N/v , 1995

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Attachment 1 List of the submittals Previously Transmitted to the NRC for Review and Approval

1. J. F. Opeka letter to the U.S. Nuclear Regulatory Commission, " Proposed Revision to Technical Specifications, 24-Month Fuel Cycle - Containment Type B and Type C Testing and Steam Generator Tube Inspections and Request for Exemption from 10CFR50, Appendix J," dated May 1, 1995. ,

2. J. F. Opeka lotter to the U.S. Nuclear Regulatory Commission, " Proposed Revision to Technical Specifications, 24-Month Fuel Cycle," dated May 1, 1995.

3. J. F. Opeka letter to the U.S. Nuclear Regulatory Commission, " Proposed Revision to Technical Specifications -

24-Month Fuel Cycle, Electrical Power Systems - Surveillance Extensions," dated June 14, 1995.

4. J. F. Opeka letter to the U.S. Nuclear Regulatory Commission, " Proposed Revision to Technical Specifications -

24-Month Fuel Cycle -

Plant System, Surveillance Extensions," dated June 29, 1995.  !

5. J. F. Opeka letter to the U.S. Nuclear Regulatory Commission, " Proposed Revision to Technical Spec 3fications -

24-Month Fuel Cycle -

Emergency Core Cooling Systems -

Surveillance Extensions," dated July 14, 1995.

6. J. F. Opeka letter to the U.S. Nuclear Regulatory '

Commission, " Proposed Revision to Technical Specifications -

24-Month Fuel Cycle -

Plant Systems, Surveillance Extensions," dated July 17, 1995.

7. J. F. Opeka letter to the U.S. Nuclear Regulatory Commission, " Proposed Revision to Technical Specifications -

24-Month Fuel Cycle - Reactor Coolant System, Surveillance Extensions," dated July 18, 1995.

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i Docket No. 50-423 9 B15306 j l

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.i Attachment 2 Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specifications i 24-Month Fuel Cycle  !

Instrumentation  !

Surveillance Extensions f

Marked-Up Pages  ;

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July 1995 ,

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Proposed Revision to Technical Specifications 24-Month Fuel Cycles P&ge Number and section Title Amendment Number 2.2.1 Reactor Trip System 2-7, 2-8 Amendment No. 85 Instrumentation Setpoints 2-4, Jan. 1986, 2-9, 2-11 Amendment No. 60 2-6,2-10, 2-12, Amendment No. 114 2-5, Amendment No. 116 Bases Reactor Trip System B 2-3, Jan. 1986 2.2.1 Instrumentation Setpoints B 2-4, Amendment No. 116 3.3.1 Reactor Trip System 3/4 3-1, 3-11, 3-12, 3-14*

Instrumentation Amendment 100 3/4 3-6, Amendment 60 3/4 3-13*, Amendment 109 3/4 3-10, Amendment 116 3.3.2 Engineered Safety Features 3/4 3-15, Amendment 91 Actuation System 3/4 3-16, 3-36, 3-37*, 3-38, Instrumentation 3-39, 3-40, 3-41*,

Amendment No.

100 3/4 3-26 Amendment No. ,

60 '

3/4 3-27 Amendment No.

67 3/4 3-28 Amendment No.

52 3/4 3-29 Amendment No.

89 3/4 3-30 Amendment 98 ,

3/4 3-31* Jan 1986 l l

3.3.3.5 Remote Shutdown 3/4 3-53, 3-58* Amendment Instrumentation 100 3/4 3-54* Amendment 56 3/4 3-55*, 3-56*,

3-57* Jan 1986 3-61* Amendment 76 3.3.3.6 Accident Monitoring 3/4 3-59*, 3-59a*, 3-61*

Instrumentation Amendment 76 3/4 3-60* Amendment 46 3/4 3-62* , 3-63*

Amendment 100 Bases RTS and ESFAS Instrumentation B 3/4 3-1 Jan 1986 3/4.3.1 and B 3/4 3-2 Amendment 91 3/4.3.2 4.2.3.1.4, Power Distribution Limits-- 3/4 2-20 Amendment 100 4.2.3.1.5, Reactor Coolant System Total 3/4 2-21 Amendment 60 4.2.3.1.6 Flow Rate--Four Loop Operation

4.2.3.2.4, Power Distribution Limits-- 3/4 2-23 Amendment 100 4.2.3.2.5, Reactor Coolant System Total 4.2.3.2.6 Flow Rate-Three Loop operation Table 4.3-3 Radiation Monitoring 3/4 3-45 Amendment 100 Instrumentation Table 4.5-8 Radioactive Liquid Effluent 3/4 3-72 January 1986 Monitoring Instrumentation 3/4 3-73* January 1986 Table 4.3-9 Radioactive Gaseous Effluent 3/4 3-78 January 1986 Monitoring Instrumentation 3/4 3-79 January 1986 3/4 3-80* January 1986 l

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• No changes are required. These Pages are provided for information only.

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