ML20136H925
| ML20136H925 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/19/1985 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20136H931 | List: |
| References | |
| NUDOCS 8511250231 | |
| Download: ML20136H925 (3) | |
Text
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A UNITE 3 STATES I
NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D, C. 20666
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GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 91 License No. DPP-16 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by GPU Nuclear Corporation and Jersey Central Power and Light Company (the licensees) dated October 11, 1985, as revised October 18, 1985 and supplemented October 22, 1985, 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 caerate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
Thereisreasonableassurance(1)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (11) 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 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 Comission's regulations and all applicable requirements have been satisfied.
0b11250231 051019 DH ADOCK 0500 19
2 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendmentandParagraph2.C.(2)ofProvisionalOperatingLicense No. DPR.16 is hereby amended to read as fellows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 91, are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment became effective October 18, 1985.
FOR THE NyCLEAR REGULAT RY OMMIS$10N Y*
John A. Zwolinski, Chief Opera ing Peactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 19, 1985 i
.D d
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ATTACHMENT TO LICENSE AMENDMENT NO. 91 PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Revise Appendix A Technical Specifications by removing the pages identified below ard inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain vertical lines indicatirg the area of change.
REMOVF INSERT 3.1-10 3.1-10 3.1-14 3.1-14 i
I
s 4
TAPLE 3.1.1 PROTECTIVE INSTRUPENTATION Reft!!REMENTS (Continued)
Min. No. of Reactor Podes Min. No. of Operable in which Function Operable or Instrument Must be Operable Operating Channels per (Tripped) Trip Operable Action Function Trip Setting Shutdown Refuel Startup Pun Systems Trip Systems Pequired*
- 2. Low-Low-24'8" above X(v)
X(v)
X(v)
X 2
2 See note h Low Reactor top of Water Level active fuel
- 3. AC Yoltage NA X(v)
X 2
2 Prevent auto depressuri
- zation on loss of AC power. See note i H. Isolation Condenser Isolation
- 1. High Flow 6.20psig P X(s)
X(s)
X X
2 2
Isolate Affected Steam Line Isolation con-
- 2. High Flow
$27"PHO X(s)
X(s)
X X
2 2
densor, comply 2
Condensate with Spec. 3.8 Line See note dd I. Offgas System Isolation
- 1. High
$ 10 x Stack X(s)
X(s)
X X
1 2
Isolate reactor Pediation Release limit or trip the In Offgas (See 3.6-A.1)
Inoperable Line (e) instrument channel J. Reactor Butiding Isolation and Standby Gas Treatment System Initiation Isolate Reactor Bldg. &
Initiate Standby Gas
- 1. High Radiation $100 Mr/Hr X(w)
X(w)
X 1
1 Treatment System or k
Reactor Building Manual Surveillance for g
Operation Floor not more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 3
(total for ill instru-
- 2. Peactor Bldg.
S17Mr/Hr X(w)
X(w)
X X
1 1
ments under J) In any 30-day period Ventilation Exhaust
~~
?
- 3. High Drywell
$?.4psig X(u)
X(u)
X X
1(k) 2(k)
N Pressure P
- 4. Low Low 1 7'2" above X(co)
X X
X 1
2
'd y
Reactor Water top of active 7
l Level fuel g
TABLE 3.1.1 (Cont'd)
~
~
.~
These functions not required to be operable then the ADS is not required to be operable.
v.
These' functions aust be operab1e only when irradiated fuel is in the fuel pool ier reactor vessel w.
and secondary containment integrity is regtfred per specification 3.5.B.
/
y.
The manber of operable channels may be reduced. to 2 per Specification 3.9-E and F. '
The bypass function to pensit stram reset in the shutdown or hfuel mode with control rod block z.
must,be operable in this mode.,,
~
Pump' circuit breakers will be, tripped in 10 seconds + 15% during a LOCA by relays.SK7A and SK8A.
aa.
bb.' Pump circuit breakers will trip;1astantaneously during a LOCA.
2 Only appilcable during startup.shode while operating in IllM range 10.
cc.
i.,.
dd. If'an isolation condenser inlet (steam side) isolation valve becomes or is made' inoperable in the open position during the run mode comply with Specification 3.8.E.
If an AC motor-operated outlet (condensate return) isolation valve becanes.or is made inoperable in the open position during the run nede comply with Specification 3.8.F.
ce. - With the number of operable channels one less than the Min. No. of Operable Instnament Channels per
- Operable Trip Systems, operation may proceed untti perfonnance of the next required Channel Functional Test provided the inoperable channel is placed in the tripped condition within I hour.
(f.. This function is not required to be operable when the associated safety bus is not required to be energized or fully operable as per applicable sections of, these technical specifications.
ii R.
- 39. These functions are not required to be operable when secondary containment is not required 2
to be maintalped or when the condittens of Sections 3.5.b.1.a. b, c. and d are met, and a
reactor water level is closely monitored and logged hourly. The Standby Gas Treatment System will be manually initiated if reactor esater level drops to the low level trip set point.
=o This note is appifcable only during the Cycle 10M outage.
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