ML20080B953
| ML20080B953 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/06/1984 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080B956 | List: |
| References | |
| NUDOCS 8402070333 | |
| Download: ML20080B953 (8) | |
Text
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UNITED STATES 3
NUCLEAR REGULATORY COMMISSION WASHINGTO N, D. C. 20555 6"U NUCI EAR _fg'03AT(UN AND JERSEY CENTRAL P0llER & LIGHT COMPANY.
0YSTER CREEK NUCLEAR GENERATING STATION AMENDfiENT'TO THE AMENDED PROVISIONAL OPERATING LICENSE Amendment No. 72 License No. DPR-16 1.
The Nucim r Regulatory Ccenission (the Commission) has found that:
A.
The application for amendment by GPU Nuclear Corporation and Jersey Central Power and Light Company (the licensees) dated March 31, 1983, 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 requirenents have been satisfied.
B402070333 840206 PDR ADOCK 01i000219 P
. 2.
Accord;ngif, the license is emnded by thatars to the Technical Specifi d ions as i-dicated in the attachment t.: i. hic license amens +ni en! Poragraph 2.C(?) of Provisional Oprreting License No. l% -iG ic-herchj (": ended to read.as followe,:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amer.dment No. 72, are hereby incorporated in the license.
GPU Nuclear Corporation 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
'))5l Dennis M. Crutch.ield, hief Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 6,1984
ATTACHMENT TO LICEllSE AMEf!Df1ENT N0. 72 PROVISIONAL OPERATING LICENSE fif'. DPR-16 DOCKET I40. 50-219 Repicce the following pages of the hr ndix A Technical Specificatier.s with the enclosed pages.
The revised pages are irientified by the captiened amendment number and contain vertical lines indicating the area of change.
PAGES 3.1-10 3.1-14 3.8-1 3.8-2 3.8-3 (new page)
3.1-1f1 -
TABLE 3.1.1 PRUfECTIVE INSTRUMENTATION REQUIREMENTS (Continued)_
Min. Nr:. n!
j Reactor Moden Min. No. of Ope rabic in Which Function Operable or Instrument Must be Operable Operating Channels Per (Tripped) Trip Operable!
Action Fu nc t ion Trip Setting Shutdown Re fuel Startup Run Systems Trip Syntems Required *
- 2. Thw-Low-Low 14'8" above X(v)
X(v)
X(v)
X 2
2 See note h
-Reactor Water top of Level active fuel
- 3. AC Voltage NA X(v)
X 2
2 Prevent auto depressurization on loss of AC mwer. See note i
~
l
- 11. Isolation Condenser Isolation
- 1. Iligh Flow Steam
$20psig P X(s)
X(s)
X X
2 2
Ir.clate Affected Isolation con-HO X(s)
X(s)
X
.' X 2
2 denaer, comply Line
- 2. liigh Flow Con-127" P 2
vi ch S pec. 3.8 j
densate line se e flo te cc -
Isolate. reactor I. Of f gas System Isolation 1.lligh Radiation
,$10 x Stack X(s)
X(s)
X X
1 2
or trip the Inoperabic in-In Of f gas Line Release limit o t tv nent channel l
(e)
(See 3.6-A.1)
Caolate Reactor J. Reactor Building Isolation and IU c'g. & Initiate i
Standby Cas Treatment System Standby Cas Treat <
- 1. liigh Radiation
$100 Mr/Hr X(w)
X(w)
X 1
1 ncnt System, or Initiation Manual Surveill-Reactor Building anc e for not more Operation Floor
- 2. Reactor Bldg.
417 Mr/Hr X(w)
X(w)
X X
1 1
than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (total for all Ind i
Ventilation otruments und er
- 3. liigh Drywell n2 psig X(u)
X(u)
X X
1(k) 2(k)
J) In any 30-day Exhaust period Press u re
- 4. Low Low Reactor 17 ' 2" above X
X X
X 1
2 Wa t er Level top of" active fuel i
Amendment No. M 72 Civinge tio. [
m 3.1-14 TABLE 3.1.1' (Cont 'd)
These functions not required to be operable when the ADS is not required to be operabic.
v.
v.
These functions must be operable only when irradiated fuel is in the fuel pool or reactor vessel nnd secondary containment integrity is required per specification 3.5.B.
y.
The number of operable channels may be reduced to 2 per Specification 3.9-E and F.
The bypass function to permit scram reset in the shutdown or refuel mode with control rod bl.ock must be operable l z.
in this mode.
l Pump circuit breakers will be tripped in 10 seconds + 15% during a LOCA by relays SK7A and SK8A.
I an.
bb.
Pump circuit breakers will trip instantaneously during a LOCA.
ec.
If an isolation condenser inlet (steam side) isolation valve becomes or is made inoperable in the open posf tion during the run mode comply with Specification 3.8.E.
If an AC motor-operated cutlet (condensate re turn) isolation valve becomes or is made inoperable in the open position durinr, the run mode comply with Specification. 3.8.F.
Amendment No. X Jg; y,5, 72 o
8 e
f
e 3.8-1 3.8 ISti.ATION CC"N PbER
/,;v 1 i cahi 1 i t y: A; ni f
.y r a t, y, n t a t e.; o f i h e i tmi n t ion cond u.acr.
c.
- ~ ~ ~ ~ULj e c t ive :
To. -:.u r e he.2 L t emovd c,; ahility un.ler conditions of reactor sessel icolation f rom its normal heat sink.
S pecificatio n: A.
The two isolation condenser loops shall be operable during power operation and whene er the reactor coolant temperature is grea'ter than 212 F except as specified in C, 0
below.
B.
The shell side of each condenser shall contain a minimum water volume of 22,730 gallons. If the minimum volume cannot be maintained or if a source of makeup water is not available to the condenser, the condenser shall be considered inoperable.
C.
If ane isolation condenser becomes inoperable during the
~
run mode the reactor may remain in operation for a period not to axceed 7 days provided the motor operated isolation and condensate makeup valves in the operable isolation condenser are demonstrated daily to be operable.
D.
If Specification 3.8. A and 3.8.B are not met, or if an inoperable isolation condenser cannot be repaired within 7 days, the reactor shall be placed in the cold shutdown condition.
E.
If an isolation condenser inlet (steam side) isolation valve (V-14-30, 31, 32 or 33) becomes or is made inoperable, in the open position during the run mode, the redundant inlet isolation valve shall be demonstrated operable.
If the inoperable valve is not returned to service within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> declare the af fected isolation l
condenser inoperable, isolate it and comply with l
Specification 3.8.C.
F.
If an AC motor-operated isolation condenser outlet (condensate return) isolation valve (v-14-36 or 37) becomes
(
or is made inoperable in the open position in the run mode, return the valve to service within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the af fected isolation condenser inoperable, isolate it and comply with Specification 3.8.C.
Amendment No. 72,
l'
.-r
L.
3.8-2 Ba si s :
The purpose of the isolation condenser is to depressurice the reactor and to remove reactor decay heat in the event that the t urbine ncnerator and main corsiencer is unavailable as a heat sink.(1) Sirce the siell side of the isolation condeneers or rate at atmospheric pressure, they c:.a accompi tah th'ir 4
pu r po r e vlie n t h e reacter tempnra tum is st:f T;cii nr ty nhovc 2]?"F ta provide (cr LW beat t ram,f er cor re puli ng to react or duay heat.
The tun side of the is lation con;!cnsers forn a closed loop with the mact cr sessel end can operate witkut redecin5 the reactor coolant water inventory.
Each condenser containing a minimum total water volume of 22,730 gallons provides 11,060 gallons above the condensing tubes.
Based on scram from a reactor power level of 1950 MWt (the design basis power level for the isolation condensers) the condenser system can accommodate the reactor decay heat (2,3)
(corrected for U-239 and NP-239) for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 40 minutes without need for makeup water. One condenser with a minimum water volume of 22,730 gallons can accommodate the reactor decay heat for 45 minutes af ter scram from 1950 MWt before makeup water is required.
In order to accommodcte a scram from 1950 MWt and cooldown, a total of 107,500 gallons of makeup water would be required either f rom the condensate storage tank or f rom the fire protection system. Since the rated reactor power is 1930 MWt,the above calculations represent conservative estimates of the isolation condenser system capability.
The vent lines from each of the isolation condenser loops to the main steam lines downstream of the main steam lines isolation valves are provided with isolation valves which close automatically on isolation condenser actuation or on signals which close the main steam isolation valves. Radiation monitors on the condenser shell side vents and the associated alarms in the control room are provided to alert the operator of a tube leak in the isolation condenser. High temperature sensors in the isolation condenser and pipe areas cause alarm in the control room to alert the operator of a piping leak in these areas.
Specification 3.8.E allows reduction ~in redundancy of isolation capability for isolation condenser inlet (steam side) isolation valves. Reasonable assurrance of isolation capability is provided by testing the operability of the redundant valve.
Specification 3.8.F allows short term inoperability of the AC motor-operated isolation condenser outlet (condensate return) valve. It is not necessary to test the redundant DC motor-operated valve as this valve is normally in the closed position. These specifications permit troubleshooting and repair as well as routine maintenance, such as valve stem packing addition or replacement, to be performed during reactor operation without reducing the redundancy of the isolation condenser heat sink func tion. The out of service time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is consistent with that permitted f or primary contair=ent isolation valve s. (5)
Ame ndment No. 72 Change No.,7
3.8-3 Either of the two icolation condensers can accomplish the purpose of the r.j a t em.
It ene conJenr.er is found to be i n spcra bl e, there is no i n ndiate thre.it to the 1(at rc:o. val capability for the reactor.ind reuc t en gera t ic: :.y continue whil. repa ir:: ar e being made.
Therefore, 'he t):e out ur service for one of LN corden sers i n ha m.. d on consfa r.,tionc %r a on. emt of two syvecr. W The L: et !nter'. ]
<.g rah!ilty of the e,1 ve c required to pince the icolntion ci.ndec.uer in cpm Lion is one.c/nonth (Specifica tion 4.8). An ecceptable cut of iervice time, T, is then determined to be 10 days.
However,1f at the time the failure is discovered and the repair time is longer than 7 days the reactor will be placed in the cold shutdown condition. If the repair tim,e is no more than 7 days the reactor may continue in operation, but as'an added factor of conservatism, the motor operated isolation condenser and condensate makeup valves on the operable isolation condenser are tested daily. Expiration of the 7 day period or inability to meet the other specifications requires that the reactor be placed in the cold shutdown condition which is normally expected to take no more than 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />. The out of service allowance when the system is required is limited to the run mode in order to require system availability, including redundancy, at st artup.
Ref ere nce s:
(1) FDSAR, Volume 1, Section IV-3.
(2)
K. Shure -and D.J. Dudziak, " Calculating Energy Release by Fission Products", U.S. AEC Report, WAPD-T-1309, March 1961.
(3)
K. Shure, " Fission Product Decay Heat", in U. S. AEC Report, WAPD-ET-24, December 1961.
(4) Specification 3.2, Bases.
.(5) Specification 3.5.3.a.1.
l Amendment No. 72
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