ML20127P557
| ML20127P557 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 01/27/1993 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20127P561 | List: |
| References | |
| NUDOCS 9302010331 | |
| Download: ML20127P557 (6) | |
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UNITED ST ATES NUCLEAR REGULATORY COMMISSION
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BOST0il EDIS0fl COMPANY 00LKET NO. 50-291 PLLGRIM NUCLEAR POWER STATI0tl AMENDMENT _10 FACILITY OPERATING LI RtdE Amendment No. 146 License No. OPR 35 1.
The Nuclear RegLlatory Commission (the Commission or the NRC) has found that:
A.
The application for amerdment filed by the Boston Edison Company (the licensee) dated October 23, 1992, complies with the standards and requircments af the Atomic Energy Act of 1954, as amanded (the Act),
and the Commission'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 Commission:
C.
There is reasonable assurar.ce:
(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 set forth in 10 CFR Chapter !;
D.
The issuance of this amendment wilI 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.
l 2.
Accordingly, the license is atended by changes to the Technical Specifica-l tions as indicated in the attachment to this license amendment, and.
l paragraph 3.D of Facility Operating License No. DPR-35 is hereby amended to read as follows:
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I 9302010331 930127 PDR ADOCK 05000293 P
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a
. T chnical Specifis.1tio_n1
.J The Technical Specifications contained in Appendix A, as revised it, rough Ameneer.t No.146, 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 its dato of issuance and shall be implemenced within 30 days, FOR THE NOCLEAR REGULATORY COMMISSION lIEv t.k
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Walter R. Butler, Direc+or Project Directorate I-3 Division of Reactor Projects - t/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications l
Date of issuance:
January 27, 1993
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4 ATTACHMENT TO LICENSE AMENDMENT NO. 146 F AC l l l TY O P FAAT I Nlt_tl(Ig1_tg_ DER _n QQCKET NO. 50-fJll l
Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and i
contain vertical lines indicating the area of change.
P1 move Jgg 6
6 l
10 10 84 84 l
l 1
l L
i l
l l
l
(
q 2.0 SAFETY LIMITS i
e
, 2,1 SMETY LIMITS 2.1.1 With the reacter steam dome pressure < 785 psig 'or core flow
< 10% of rated core flow:
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THERMAL-POWER shall be s 25% of RATED THERMAL POWER.
l 2.1.2 With the-reactor steam dome pressure 2 785 psig and core flow 210% of rated core flow:
MINIMUM CRITICAL POWER RATIO shall be 2 1.07..
j 2.1.3 Whenever the raactor is in the cold shutdown. condition with-irradiated fuel in the reactor vessel, the water level shall not be less than 12 inches abov2 the top of the normal active fuel zone.
2.1.4 Reactor steam dome pressure shall be s 1325 psig at any tirne when irradiated fuel is present in the reactor vessel.
2.2 jaffJY LIMIT VIOLAT!@
With any Safety Limit not met the following actions shall be met:
2.2.1 Within one hour notify the NRC Operations Centcr in accordance with 10CFR50.72.
2.2.2 Within two hours:
A.
Restore compliance with all Safety Limits, ~and B.
Insert all insertable control rods.
2.2.3 The Station Director and Senior Vice President - Nuclear and the Nuclear Safety Review and Audit-Couittee (NSRAC) shall be notified within 24-hours.
2.2.4 A Licensee Event Report-shall be prepared pursuant to 10CFRSO.73.. The Licensee hent Report. shall be submitted to the Commission, the Operations Review Committee (ORC), the-NSRAC and the Station Director and Senior Vice President -
Nuclear within '30 days of-the violation. -
2.2.5 Critical operation of the unit shall not be resumed until t~
authorized by the Commission.
Amendment No. 15, 27, 42, 72, 133, 146 6
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g,ASES (continuedl RFACTOR The Safsty Limit for the reactor steaa dome pressure has been STEAM DOME selected such that it is at a pressure below which it can be PRESSURE shown that the integrity of the system is not ondangered.
(2.1.4)
The reactor pressure vessel is designed to Section III of the ASME Boiler and Pressure Vessel Code (1965 Editica, including the January 1966 Addendum), which permits a maximum pressure transient of 110%, 1375 psig, of design pressure 1250 psig.
The Safety Limit of 1325 psig, as creasured by the reactor steam dome pressure indicator, is equivalent to 1375 psig at the lowest elevation of the reactor coolant system. The reactor coolant system is designed to the USAS Nuclear Power-Piping Corie, Section B31.1.0 for the reactor recirculation pipirg, which permits a maximum pressure transient of 120% of design pressures of 1148 psig at 562*F for suction piping and 1241 psig at 562'F for discharge piping. The pressure Safety Limit is selected to be the lowest transient overpressure allowed by the applicable codes.
REFERE! ICES 1.
" General Electric Standard Application for Reactor Fuel,"
NEDE-240ll-P-A (Applicable Amendment specified in the CORE OPERATING LIMITS REFORT).
2.
General Electric Themal Analysis Basis (CETAB): Data, Correlation and Design Application, General Electric Co.
BWR Systems Department, January 1977, NEDE-10958 PA and NE00-10958 A.
Amendment No. 15, 133, 146 (Next page is 26) 10
LIMITING CONDITION FOR OPERATION SURVEllQNCE RE0VIRQiUE 3.3.C Stram Insertion Tin.g 4.3.C Scram Intertion Timg
'2. The average of the scram 2.
Within each 120 days of insertion times for the three operation, a minimum of 10%
f astest control rods of a 1 of the control rod drives, groups of four control rods on a ' rotating basis, shall in a two by two array shall be scram tested as in be no greater than:
4.3.C.l.
An evaluation shall be completed every
% Inserted Avg. Scram 120 days of operation to from Fully Insertion provide reasonable Withdrawn _
Jime Sec.
assurance that proper performance is being 10
.58 maintained.
30 1.35 50 2.12 90 3.71 l
1,
- 3. The maximum scram insertion time for 90% inserticn of any operaole control rod shall not exceed 7.00 seconds.
D. C ptrol Rod Accumulators D.
Control RoLA,,gcum.yj ators 9
At all reacter operating Once a shift, check the status pressures, a red accumulator of the pressure and level may be inoperable provided alarms for ezch accumulator, that no other control rod in the nine-rod square array around this rod has a:
1.
!noperable acccmulator.
2.
Directional control valve electrically disarmed while in a non-fully inserted position.
3.
Scram insertion time greater than the maximum permissible insertion time.
If a control rod with an inoperable accumulator -is inserted " full-in" and its directional control valves are electrically disarmed, it shall not be considered to have an inoperable accumulator.
Amendment No. 65,-124, 146 84
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