ML20150F165
| ML20150F165 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 07/08/1988 |
| From: | Wessman R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20150F168 | List: |
| References | |
| NUDOCS 8807180163 | |
| Download: ML20150F165 (5) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION 3,
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BOSTON EDIS0N COMPANY DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.119 License No. DPR-35 1.
The Nuclear Regulatory Comission (the'Comission) has found that:
A.
The application for amendment by Boston Edison Company (the licensee) dated December 23, 1985 as supplemented on February 22, 1988 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's 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 Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the pub 13c, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the licinse is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 9.B of Facility Operating License No. DPR-35 is hereby amended to read as follows:
8807180163 880708 PDR ADOCK 050 93 P
2 (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 119
, 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 issuance and shall be implemented within 30 days.
FOR THE NUCLEAR P.EGULATORY COMMISSION Richard H. Wessman, Director Project Directorate I-3 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 8, 1988 L
i
' ATTACHMENT TO LICENSE AMEN 0 MENT NO. 119 FACTETTV DPERATTRG ETCERIE KD! DPR 35
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'f Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Paces inser-28 i
46 46 e
d
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NOTES FOR TABLE 3.1.1 i
1.
There shall be two operable or tripped trip systems for each function. An instrument channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the trip system in the trip rd condition provided at least one OPERABLE channel in the same trip systen is monitoring that parameter.
If the minimum number of operable instrument channels per trip system cannot be met for both trip systems, the appropriate actions listed below shall be taken.
A.
Initiate insertion of operable rods and complete insertion of all operable rods within four hours.
8.
Reduce power level to IRH range and place mode switch in the startup/
hot standby position within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
C.
Reduce turbine load and close main steam line isolation valves within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
D.
Reduce power to less than 45% of design.
2.
Permissible to bypass, with control rod block, for reactor protection system reset in refuel and shutdown positions of the reactor mode switch.
3.
Permissible to bypass when reactor pressure is (600 psig.
4.
Permissible to bypass when turbine first stage pressure is less than 305 psig.
5.
IRH's are bypassed when APRH's are onscale and the 'eactor mcde switch is in the run position.
6.
The design permits closure of any two lines withoJt a scram being initiated.
7.
When the reactor is subcritical, fuel is in the reactor vessel and the reactor water temperature is less than 212'F, only the following trip functior.s need to be operable:
A.
Mode switch in shutdown B.
Manual scram C.
High flux IRH D.
Scram discharge volume high level E.
APRH (15%) high flux scram 8.
Not required to be operable when primary containment integrity is not required.
9.
Not required while performing low power physics tests at atmospheric pressure during or after refueling at power levels not to exceed 5 MW (t).
Amendment No.119 28
1 M LOR TABLE 3.2.A 1.
Whenever Primary Containment integrity is required by Section 3.7, there shall be two operable or tripped trip systems for each function. An instrument channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required survelliance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter; or, where only one channel ed sts per trip system, the other trip system shall be operable.
2.
Action If the first column cannot be met for one of the trip systems, that trip system shall be tripped.
If the first column cannot be met for both trip systems, the appropriate action listed below shall be taken.
A.
Initiate an orderly shutdown and have the reactor in Cold Shutdown Condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B.
Initiate an orderly load reduction.and have Main Steam Lines isolated within eight hours.
C.
Isolate Reactor Water Cleanup System.
D.
Isolate Shutdown Cooling.
3.
Instrument set point corresponds to 128.26 inches above top of active fuel.
4.
Instrument set point c3rresponds to 77.26 iaches above top of active fuel.
5.
Not required in Run Mode (bypassed by Mode Switch).
6.
Two required for each steam line.
7.
These signals also start S8GTS and initiate secondary containment isolation.
8.
Only required in Run Mode (interlocked with Hode Switch).
9.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of hydrogen injection with the reactor power at greater than 20% rated power, the normal full power radiation background level and associated tm p setpoints may be changed based on a calculated value of the radiation level expected during the injection of hydrogen.
The background radiation level and associated trip setpoints may be adjusted based on either calculations or measurements of actual radiati n levels resulting from hydrogen injection.
The background 9
radiation lever shall be determined and associated trip setpoints shall be set within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels after completion of hydrogen injection and prior to withdrawing control rods at reactor power levels below 20% rated power.
l Amendment No. 86, 105, 178, 119 46
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