ML19274E393
| ML19274E393 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 03/02/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19274E394 | List: |
| References | |
| NUDOCS 7903260011 | |
| Download: ML19274E393 (4) | |
Text
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UNITED STATES f
.i NUCLEAR REGULATORY COMMISSION f
,h WASHINGTON, D. C. 20555 88 ts
'.%;' 4 r s
...s COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION UNIT NO. 2 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 41 License No. DPR-19 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated February 28, 1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (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 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.
79032600\\\\
. 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 Provisional Operating License No. DPR-19 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 41, 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 its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 7[.
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J /rvi e A
'Ne Dennis L. Ziemann, C W'ef Operating Reactors Branch #2 Division of Operating Reactors
Attachment:
Changes to the Technical Speci fications Date of Issuance: March 2,1979
ATTACHMENT TO LICENSE AMENDMENT N0. 41 PROVISIONAL OPERATING LICENSE NO. DPR-19 DOCKET NO. 50-237 Change the Technical Specifications contained in Appendix A by removing Page 91b and inserting the enclosed Page 91b.
The revised page contains the captioned amendment number and a vertical line indicating the area of change.
l 4.6 SURVEILLANCE REOUIRL:.E':T 3.6 LI:'.IT Im C OND I'cIO:! Kn GPE2A'_'IO::
I i
i 1.
Shock Suppressers (Snubbers) 1.
Shock Suppr..ssors (Snubbers)
The following surveillance requ iro -
1.
During all modes c; operation ments apply to all hydraulic snubbers cold shutdown and refuel, listed in Table 3.6.1.
excene all. saf ety-related snubbers listed in Table 3.6.1 chall be operable 2 10.t l All hvdraulic snubbers the:
except as noted in Specification 1.
w.erial nas been henstrucc.W
' b t25 tin 3 or operating exnerience,to be.:0.maatible rith tna 3*6*I*^' tP ouch 3*6*I*4*
a.alysis
- hall be vi39 ally operating environment 2.
Frcm and after the time that a in nectc-d.
This inr 2Ci. ion shall in-snubber is determined to be inoperable, cluda, but not necel': rily be li".itsi to, incpcetion 'n the Pfd:1ulic flu l.r :-
EEVO iT : fluid c:nnac Lonc, and 'inAage continued reactor operation is perraissible ancoor, o varify anubbar cea_aat.(g and only during the succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> unless connection to the clo n _ts '.n 3; wrainca the snubber is sooner nade operable or with tha followihg. c.odule:
I replaced.
3.
I f th reqcirements of 3.6.I.1 and of Snubters Found No.
Next Raquired 3.6.1. 2 can not be not, an orderly Inoparable During In-shutdown shall be initiated and the scection Interval Insnection In t e r v '.1 reactor shall be in cold chutdown or 18 months 1 25%
rafuel condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
O 12 months - 25%
1 6 raonths i 25%
4.
If a enubber is determined to be inoperable 2
124 days 1 233 tchile the reactor is in the cold shutdot:n or 3, 4 62 days 1 25%
refuel mode, the snubber shall be inade 5, 6, 7
'31 days + 25%
operable or replaced prior to reactor g
startup.
The required inspection intarval shall step not be lengthened more than one 5.
Snubbers may be added to safety related at a time.
systcms without prior license a:nendment a revision The required inspection interval may be to Table 3.6.1 provided that to Table 3.6.1 is included with the next extended an additional seven days from license anendment reagest*
March 10,1979 to March 17, 1979.
91 b Amendment No. M, 41
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