ML20249B831

Amend 175 to License DPR-35,modifying Plant TS Section 3.6.A.4 W/Respect to Monitoring Requirements for Vessel Flange & Adjacent Shell Differential Temp During Heatup & Cooldown

ML20249B831
Person / Time
Site:	Pilgrim
Issue date:	06/19/1998
From:	Thomas C NRC (Affiliation Not Assigned)
To:
Shared Package
ML20249B832	List: ML20249B831 ML20249B833
References
NUDOCS 9806240285
Download: ML20249B831 (5)

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NUCLEAR REGULATORY COMMISSION

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BOSTON EDISON COMPANY DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.175 License No. DPR-35

1. The Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A.

The application for amendment filed by the Boston Edison Company (the licensee) l dated March 25,1998, as supplemented on April 8, and May 5,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations; 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 Commission's 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 Commission's 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 3.B of Facility Operating License No. DPR-35 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications ce ntained in Appendix A, as revised through Amendment No.175

, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

9906240285 990619 PDR ADOCK 05000293 P

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2-3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION Cecil O. Thomas, Director Project Directorate 1-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date ofissuance: June 19, 1998

I ATTACHMENT TO LICENSE AMENDMENT NO.175 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 i

Replace the following pages of the Appendix A Technical Specifications with the attached pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Remove ingg_r1 3/4.6-1 3/4.6-1 B3/4.6-1 B3/4.6-1 I

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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.6 PRIMARY SYSTEM BOUNDARY 4.6 PRIMARY SYSTEM BOUNDARY ADDhcability.

Applicability:

Aylies to the operating status of the reactor Applies to the periodie, examination and coolant system.

testing requirements for the reactor cooling system.

Obloctive-Objective:

To assure the integrity and safe operation of To determine the condition of the reactor the reactor coolant system.

coolant system and the operation of the safety devices related to it.

Specification Specification:

A.

Thermal and Pressurization Limitations A.

Thermal and Pressurization Limitations 1.

The average rate of reactor coolant 1.

During heatups and cooldowns, temperature change during normal heatup with the reactor vessel temperature or cooldown sh' ll not exceed 100*F/hr less than or equal to 450*F, verify a

when averaged over a one-hour period the RCS heatup and cooldown except when the vessel temperatures are rates are within limits every 15 above 450*F.

minutes.

2.

The reactor vessel shall not be 2.

Reactor vessel shell temperatures, including pressurized for hydrostatic and/or leakage reactor vessel bottom head, and reactor tests, and subcritical or critical core

. coolant pressure shall be permanently operation shall not be conducted unless logged at least every 15 minutes whenever the reactor vessel temperatures are above the shell temperature is below 220*F and those defined by the appropriate curves the reactor vesselis not vented, on Figures 3.6-1, 3.6-2, and 3.6-3. (Linear interpolation between curves is permitted).

At stated pressure, the reactor vessel bottom head may be maintained at temperatures below those temperatures corresponding to the adjacent reactor vessel shell as shown in Figures 3.6-1 and 3.6 2.

Revision m u, 175

- Amendment No. '" *e 3/4.6-1

BASIS:

3/4.6 PRIMARY SYSTEM BOUNDARY A.

Thermal and Pressurization Limitations l

The allowable rate of heatup and cooldown for the reactor vessel contained fluid is 100 F per hour averaged over a period of one hour. This rate has been chosen based on past experience with operating power plants. The associated time periods for heatup and c

cooldown cycles when the 100*F per hour rate is limiting provides for efficient, but safe, L

plant operation.

1 Specific analyses were made based on a heating and cooling rate of 100'F/ hour applied continuously over a temperature range of 100'F to 546 F. Calculated stresses were within ASME Boiler and Pressure Vessel Code Se; tion III stress intensity and fatigue limits even at the flange area where maximum stress occurs.

l The manufacturer performed detailed stress analysis as shown in Amendment 17 of the FSAR. This analysis includes more severe thermal conditions than those which would be encountered during normal heating and cooling operations.

The coolant in the bottom of the vessel is at a lower temperature than that in the upper regions of the vessel when there is no recirculation flow. This colder water is forced up when recirculation pumps are started. This will not result is stresses which exceed ASME Boiler and Pressure Vessel Code,Section III limits when the temperature differential is not greater than 145 F.

The reactor coolant system is a primary barrier against the release of fission products to the environs. In order to provide assurance that this barrier is maintained at a high degree ofintegrity, restrictions have been placed on the operating conditions to which it can be subjected.

Appendix G to 10CFR50 defines the temperature-pressurization restrictions for hydrostatic and leak tests, pressurization, and critical operation. These limits have been calculated for Pilgrim and are contained in Figures 3.6-1,3.6-2, and 3.6-3.

Revision Amendment No. 175 B3/4.6-1

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