View source for B16186, Application for Amend to License DPR-65,modifying TSs 3.3.1.1 & 3.3.2.1 to Restrict Time Most Reactor Protection or Esfa Channels Can Be in Bypass Position to 48 Hours,From Indefinite Period of Time

{{Adams
| number = ML20247G662
| issue date = 05/14/1998
| title = Application for Amend to License DPR-65,modifying TSs 3.3.1.1 & 3.3.2.1 to Restrict Time Most Reactor Protection or Esfa Channels Can Be in Bypass Position to 48 Hours,From Indefinite Period of Time
| author name = Bowling M
| author affiliation = NORTHEAST NUCLEAR ENERGY CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000336
| license number = 
| contact person = 
| document report number = B16186, NUDOCS 9805200316
| package number = ML20247G670
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS &amp; PERMITS
| page count = 3
| project = 
| stage = Request
}}

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{
P.O. Box 128 Watedord, Cr 06385-0128 (860) 447-1791 Fax (860) 444-4277 The Northeast Utilities System MAY I 41998 Docket No. 50-336 B16186 Re: 10CFR50.90 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Reactor Protective and Engineered Safety Feature Actuation System Instrumentation Introduction Pursuant to 10CFR50.90, Northeast Nuclear Energy Company (NNECO) hereby proposes to amend Operating License DPR-65 by incorporating the attached proposed changes into the Technical Specifications of Millstone Unit No. 2. The proposed changes modify Technic-l Specifications 3.3.1.1, " Reactor Protective Instrumentation" and 3.3.2.1, " Engineered Safety Feature Actuation System Instrumentation" to restrict the time most reactor protection or engineered safety feature actuation channels can be in the bypass position to 48 hours, from an indefinite period of time.
NNECO is also proposing to modify the Technical Specification action requirement for                j the loss of turbine load reactor trip function, the channel calibration requirements for                 l the loss of turbine load reactor trip function and the wide range logarithmic neutron flux            j monitors, add a note to exclude neutron detectors from channel calibration requirements, correct a reference to a surveillance requirement, and correct errors contained on Technical Specification Page 2-4.                                                      N[;
Attachment 1 provides a discussion of the proposed changes and the Safety Summary.
At'schment 2 provides the Significant Hazards Consideration. Attachment 3 provides the marked-up version of the appropriate pages of the current Technical Specifications.
Attachment 4 provides the retyped pages of the Technical Specifications. Attachment 5 provides the history for Technical Specification Page 2-4, from License Amendment 3
98r)5200316 980514 PDk     ADOCK 05000336 P                     PDR

U. S. Nuclear Regulatory Commission B16186/Page 2 No. 52 to License Amendment No.199, and Page 2-5, from License Amendment No.
52 to License Amendment No. 61.
Environmental Considerations NNECO has reviewed the proposed License Amendment Request against the criteria of 10CFR51.22 for environmental considerations. The proposed changes will restrict the time most reactor protection or engineered safety feature actuation channels can be in the bypass position, modify reactor protection channel surveillance requirements, and correct various minor Technical Specification errois. These changes do not increase the type and amounts of effluents that may be released off site. In addition, this amendment request will not significantly increase individual or cumulative occupational radiation exposures. Therefore, NNECO has determined the proposed changes will not have a significant effect on the quality of the human environment.
Conclusions The proposed changes were evaluated utilizing the criteria of 10CFR50.59 and were determined to involve an unreviewed safety question. One of the proposed changes will allow two pressurizer high pressure reactor protection channels to be removed from service (one channel in the tripped condition and one channel in the bypassed condition) for 48 hours instead of the current 2-hour time limit. With a pressurizer pressure channel in the tripped condition, the high failure of a second pressurizer pressure channel would initiate a reactor trip and open both pressurizer power operated relief valves (PORVs).
Opening the pressurizer PORVs would result in an undesired loss of primary coolant.
Thus, this change will increase the probability of occurrence of a previously evaluated accident. However, since this configuration will only be allowed for an additional 46 hours, the increase in the probability of occurrence of a previously evaluated accident will be limited to an acceptable value. Therefore, we have concluded that the proposed changes are safe.
The proposed changes do not involve a significant impact on public health and safety (see the Safety Summary provided in Attachment 1) and do not involve a Significant Hazards Consideration pursuant to the provisions of 10CFR50.92 (see the Significant Hazards Consideration provided in Attachment 2).
Plant Operations Review Committee and Nuclear Safety Assessment Board The Plant Operations Review Committee and Nuclear Safety Assessment Board have reviewed and concurred with the determinations.
Schedule We request issuance at your earliest convenience, with the amendment to be implemented within 60 days of issuance.

U. S. Nucisar Regulatory Commission B16186/Page 3 State Notification in accordance with 10CFR50.91(b), a copy of this License Amendment Request is i_              being provided to the State of Connecticut.
If you should have any questions on the above, please contact Mr. Ravi Joshi at (860) 440-2080.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY M. L. Bowling, Jr.         G Recovery Officer - Technical Services Sworn to and subscribed before me this    /    day of      MdV                  1998
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P(gtary Pubic My Commission expires KboM.9001 Attachments (6) cc:      H. J. Miller , Region I Administrator D. G. Mcdonald, Jr., NRC Project Manager, Millstone Unit No. 2 D. P. Beaulieu, Senior Resident inspector, Millstone Unit No. 2 W. D. Travers, Ph.D, Director, Special Projects Office W. D. Lanning, Director, Millstone Assessment Team Director Bureau of Air Management Monitoring and Radiation Division Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127
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