ML030640412

Request for Amendment to Technical Specifications Changes to Post Accident Monitoring Instrumentation Requirements, Supplement

ML030640412
Person / Time
Site:	Pilgrim
Issue date:	02/14/2003
From:	Dugger C Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML030640412 (4)

Text

Entergy Nuclear Operations, Inc.

" Entergy Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 Charles M. Dugger Vice President - Operations February 14, 2003 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station O-P1-17 Washington, DC 20555-0001

SUBJECT:

Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station Docket No. 50-293 License No. DPR-35 Request for Amendment to the Technical Specifications Changes to Post-Accident Monitoring Instrumentation Requirements

REFERENCE:

1) Entergy Letter 2.02.065, R.M. Bellamy to NRC, "Request for Amendment to the Technical Specifications Relocation of Certain Control Rod Block Requirements to the Updated Final Safety Analysis Report," dated August 16, 2002

2) Entergy Letter 2.02.072, R.M. Bellamy to NRC, "Request for Amendment to the Technical Specifications Changes to Post-Accident Monitoring Instrumentation Requirements," dated August 19, 2002 LETTER NUMBER: 2.03.019

Dear Sir or Madam:

In accordance with the provisions of 10 CFR 50.90, Entergy Nuclear Operations, Inc. (Entergy) is submitting a supplementary change to the Reference 2 request for an amendment to the Technical Specifications (TS) for Pilgrim Nuclear Power Station. This supplementary information restores the portion of Note 2 on TS page 3/4.2-41 associated with Tables 4.2.D and 4.2.G.

This proposed change does not impact the conclusions of the previously submitted no significant hazards conclusions. Attachment 1 provides the revised proposed mark-up of the affected page.

The mark-up of the TS submitted with this supplementary change restores Note 2 on TS page 3/4.2-41, with the exception of one sentence that was deleted in the original submittal and which is still no longer needed. Deletion of the marked-up sentence from Note 2 is dependant upon the prior approval of the proposed TS change concerning the relocation of certain Control Rod Block functions submitted via Reference 1. If the changes requested in Reference 1 are not approved prior to the approval of this proposed change, then the marked-up portion of Note 2 should not be deleted as part of this change.

203019

Entergy Nuclear Operations, Inc. Letter Number: 2.03.019 Pilgrim Nuclear Power Station Page 2 If you have any questions, please contact Mr. Bryan Ford at (508) 830-8403.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 14th day of February 2003.

Sincerely, Charles M. Dugger

Attachment:

1. Marked-up Proposed Technical Specification page (1 page) cc:

Regional Administrator, Region I Mr. Robert Walker U.S. Nuclear Regulatory Commission Radiation Control Program 475 Allendale Road Commonwealth of Massachusetts King of Prussia, PA 19406 Executive Offices of Health and Human Services Mr. Travis Tate, Project Manager 174 Portland Street Project Directorate I Boston, MA 02114 Division of Licensing Project Management Office of Nuclear Reactor Regulation Mr. Steve McGrail, Director U. S. Nuclear Regulatory Commission Massachusetts Emergency Management Mail Stop: O-8B-1 Agency Washington, DC 20555-0001 400 Worcester Road Framingham, MA 01702 Senior Resident Inspector U. S. Nuclear Regulatory Commission Pilgrim Nuclear Power Station 600 Rocky Hill Road M/S 66 Plymouth, MA 02360 203019

ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION CHANGE (MARK-UP)

NOTES FOR TABLES 4.2.A THROUGH 4.2.G

1. Initially once per month until exposure hours (Mas defined on Figure 4.1.1) is 2.0 x 105 ; thereafter, according to Figure 4.1.1 with an interval not less than one month nor more than three months.

2. Functional tests, calibrations and instrument checks are not required when these instruments are not required to be operable or are tripped. Functional tests shall be performed before each startup with a required frequency not to exceed once per week.

Instrument checks shall be performed at least once per day during those penods when the instruments are required to be operable.

3. This instrumentation is excepted from the functional test definition. The functional test will consist of injecting a simulated electrical signal into the measurement channel.

4. Simulated automatic actuation shall be performed once each operating cycle. Where possible, all logic system functional tests will be performed using the test jacks.

5. Reactor low water level and high drywell pressure are not included on Table 4.2.A since they are tested on Tables 4.1.1 and 4.1.2.

6. The logic system functional tests shall include a calibration of time delay relays and timers necessary for proper functioning of the trip systems.

7. Calibration of analog trip units will be performed concurrent with functional testing. The functional test will consist of injecting a simulated electrical signal into the measurement channel. Calibration of associated analog transmitters will be performed each refueling outage.

Amendment No. 42, 99, 110,117, 151 3/4.2-41