ML20040G162
| ML20040G162 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/03/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20040G163 | List: |
| References | |
| NUDOCS 8202110375 | |
| Download: ML20040G162 (10) | |
Text
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e UNITED STATES I'
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NUCLEAR REGULATORY COMMISSION g
uE WASHINGTON, D. C. 20555 49.....,o GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 0YSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO AMENDED PROVISIONAL OPERATING LICENSE Amendment No. 60 License No. DPR-16 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by GPU Nuclear Corporation and Jersey Central Power and Light Company (the licensees) dated October 19 and 26,1981, comply with the standards and require-ments 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 applications, 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.
e 8202110375 820203 PDR ADOCK 05000219 l
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C(2) of Provisional Operating License No. DPR-16 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 64 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 COWilSSION l74 4 Y Dennis M. Crutchfield, ief Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Speci fications Date of Issuance:
February 3,1982 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 60 PROVIEIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Replace the following pages* of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by captioned amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT 3.1-6a 3.1 -6a 3.1 -11 a 3.1 -11 a 3.1-12a 3.1-13 3.1-14 3.7-3 3.7-3
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4.7-1 4.7-1 4.7-2 4.7-2 l
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- Pages 6-la, 6-16, 6-10 and 6-2 issued by Amendment No. 59 dated December 29, 1981 should be renumbered 6-2 through 6-5, respectively.
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8 3.1-6a-and the requirements of Table 3.1.1 are met.
In order to maintain reliability of core monitoring in that quadrant where an APRM is inoperable, it is permitted to remove the operchic APRM from service for calibratio. and/or test provided that 'the same core
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protection is maintained by alternate means.
In the rare event that Travelling In-core Probes (TIPS) are used to meet the requirements 3.1.B or 3.1.C, the licensee may perform an analysis of substitute LPRM inputs to the APRM system using spare (non-APDI input) LPR21 detcetors and change the APMt system as permitted by 10 CFR 50.59.
Under assumed loss-of-coolant accident conditions and under certain loss of offsite power conditions with no assu=ed loss-of-coolant accident, it is inadvisabic to allow the simultaneous starting of emergency core cooling and heavy load auxiliary systems.in order to minimi:e the voltage drop across the emergency buses and to protect against a potential diesel generator overload. The diesel generator load sequence time delay relays provide this protective function and are set accordingly. The repetitive accuracy rating of the timer mechanism as well as parametric analyses to evaluate the maximum acceptable tolerances for the dicscl. loading sequence timers were considered in the establishment of the appropriate load sequencing.
Manual actuation can be accomplished by the operator and 'is considered appropriate only when the auto =atic load sequencing has been completed. This will prevent simultaneous starting of heavy lead auxiliary systems and protect against the potential for diesel generator overload.
Also, the Closed Cooling Water and Service Water pump circuit breakers
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will trip whenever a loss-of-coolant accident condition exists. This is justified by Amendment 40 of the Licensing. Application which determined that these pumps'were not required during this accident condition.
Reference:
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(1) i SEDO-10189 "An Analysis. of Functional (pm=on abde Fai'lurcs in l
GE BWR Protection and Control Instrumentatio'n", L. G. Frederick, l
et. al., July 1970.
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ChangeNo.g l
Amendment No. 9,,15 [, 60 l
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3.1-lle TABl.E 3.1.1 PROTECTIVE INSTRtJM&frATION REQUIRDIENTS (cont'd)
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Min. No. of Min. No. of Operable Reactor Ibdes Operable or instrument in Which Function Operating Channels Per Must Bc Operablo (Tripped) Trip Operable Function Trip Setting Shutdown Re fuel Startup Run Systems Trip Systems Action Required
- Diesel Generator I,oad Sequence Timers (Cont'd) 2.
CRD pump 60 sec ! 15%
X X
X X
2(a) 1(n)
Consider the pump inoperable and comply with Spec.
3.4.D (See Note q).
3.
Emerg. Service 45 sec. ! 15%
X X
X X
2(m) 1(n)
Consider the loop inoperable and Water Pump (r) comply with Spec.
3.4.C (See Note q).,
(SKIA)
C'nsider the pump 1,n-4.
Service Water 420 sec ! 15% (SX2A) X X
X X
2(o) 2(p) o l
Pump (aa) 10 sec ! 15% (SK7A) operable and comply (SK8A)
' within 7 days (See Note q).
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Closed Cooling 166 sec 1 15%
X X
X X
2(m) 1(n)
Consider the pump in-Water Pump (bb)
, operable and comply within 7 days (See Note q).
l Amendment No. PT, 60
3.1-13 T_Anl.li 3.1.1 (Cont'd) 1.
The interlock is not required during the start-up test program and demonstration 'of plant electrical output but shall be provided following these actions.
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Not required below 40% of ' turbine rated steam flow.
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All four (4) drywell pressure instrument channels may be mado inoperable during the integrated primary containment leakage rate test (Sce Specification 4.5), provided that the plant is in the cold shutdown condition and that no work is performed on the reactor or its connected systems which could result in lowering the reactor water level to less than 4'8" above the top of the active fuel.
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Bypassed in IRH Ranges 8, 9, 6 10.
There is, one time delay relay. associated with each of two pumps.
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One time delay relay per pump must be operable.
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There are two time delay relays associated with 'each of two pumps. One timer per pump is for sequence o,
starting (SKI A, SK2A) and one timer per pump is for tripping the pump circuit breaker (SK7A, SK8A),
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Two time delay relays per pump must he operable.
q.
Manual 1,nitiation of affected component can be accomplished after the automatic load sequencing is completed.
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Time delay starts after closing of containment spray pump circuit breaker.
These functions not' required to bo operable with the reactor temperature less than 212*F and the vessel s.
head removed or vented.
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These functions may be operable or bypassed when corresponding portions in the same core spray system logic train are inoperable per Specification 3.4. A.
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These functions not required to be operable when primary containment integrity is not required to be maintained.
Amendment No. -t5, 4(7 60
3.1-14 TABl.E 3.1.1 (Cont'd)
These functions not required to be operable when the ADS is not required to be operable.-
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These functions must be operable only when irradiated fuel is in the fuel pool or teactor vessel w.
and 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.
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(LEFT INTENTIONALLY BLANK) aa. Pump circuit breakers will be tripped in 10 seconds 1 15% during a LOCA by relays SK7A and SK8A.
bb. Pump circuit breakers will trip instantaneously during a LOCA.
i Amendment No. M, 60
3.7-3 The probability analysis in Appendix "L" of the FDSAR was, based on one diesel and shows that even with only one diesel the probability of requiring engineered safety features at the same time as the second diesel fails is quite small. This analysis used information on peaking diesels when synchroni:ation was required which is not the case for Oyster Creek. Also the daily test of the second diesel when one is temporarily out of service tends to improve the reliability as does the fact that synchroni:ation is not required.
As indicated in Amendment 18 to the Licensing Application, there are numerous sources of diesel fuel which can be obtained within 6 to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and the heating boiler fuel in a 75,000 gallon tank on the site could also be used. Since the requirements for operation of the required engineered safety features after an accident or for safe shutdown can be supplied by one diesel generator the specification requirement for 14,500 gallons of diesel fuel can operate one diesel at a load of 2640 KW for 3 days. As indicated in Amendment 32 of the Licensing Application and including the Security System loads, the load requirement for the loss of offsite power would require 12,410 gallons for a three day supply. For the case of loss of offsite power plus loss-of-coolant plus bus failure 9790 gallons would be required for a three day supply.
In the case of loss of offsite power plus loss-of-coolant with both diesel generators starting the load requirements (all equipment operating) shown there would not be three days' supply. However, not all of this load is required for three days and, after evaluation of the conditions, loads not required on the diesel will be curtailed.
It is reasonable to expect that within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> conditions can be evaluated and th. following loads curtailed:
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One Core Spray Pu=p 2.
One Core Spray Booster Pump 3.
One Control Rod Drive Pump 4.
One Containment Spray Pump S.
One. Emergency Service Water Pump With these pieces of equipment taken off at 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the incident it would require a total consumption of 12,840 gallons for a three day supply.
References :
(1) Letter, Ivan R. Finfrock, Jr. to the Director of Nuclear Reactor Regulations dated April 14, 1978.
Amendment No.,E5,60
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4.7-1 t
4.7 AUXILIARY ELECTRTCAL POWER 4h".
)hh>licab'l lity:
Appli.es to,sdrveillance requirements'of the auxiliary' electrical, supply.
Objective:
To verify the availability of the auxiliary electrical supply.'
Specification:
A.
Diesel Generator 1.
Each diesel generator shall be started and loaded to not less.than 205 rated power every two weeks.
2.
The two diesel generators shall be automatically actuated and functionally tested during each refueling outage. This shall include testing of the diesel generator load sequence timers listed in Table 3.1.1.
3.
Each diesel generator shall be given a thorough inspection at least once per 18 months during shutdown.
4.
The diesel generators' fuel supply shall be checked following the above tests.
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5.
The diesel generators' starting batteries shall be tested and monitored the same as the station batteries, Specification 4.7.b.
l Amendment No. Js; 60 4
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. Basis:
The. biweekly tests.or.the diesel generators ade primarily to check for fallgres and deterioration in-the system since last use. ' The manuf acturer has recommended the two week test interval, based on experience with many of thede engines.
One factor in determining this test interval (besides checking whether or not the engine starts and runs) is that the lubricating oil should be circulated through the engine approximately every two weeks. The diesels should be loaded to at least 20% of rated power until engine and generator temperatures have stabilized (about one hour).' The-minimum 20% load will prevent soot formation in the cylinders and-lejection nozzles. Operation up to an equilibrium
- 1emperature ensures that there is no over-heat problem.
.The tests also provide an engine and generator operating history to be compared with subsequent engine-generator test data to identify and correct any mechanical or electrical deficiency before it can result in a system failure.
The test during refueling outages is more comprehensive, including procedures that are most effectively. conducted at that time. These include automatic actuation and functional capability tests, to verify that the generators can start and assume load in less than 20 seconds and testing of the diesel generatcr load sequence timers which provide protection from a possible diesel gener.ater overload during LOCA conditions. Thorough inspections will detect any signs of wear long before~ failure.
The manufacturer's instructions for battery care and mainten-ance with regard to the floating charge, the e.qualizing l
charge, and the addition of water will be followed.
in addition, written records will be maintained o,f the battery performance. Station batteries will deteriorate with time, but precipitous failure is unlikely. The station surveillance procedures follow the recommended maintenance and testing practices of IEEE STD. 450 which have demonstrated, thorough experience, the ability to provide positive indications of cell deterioration tendencies long before such tendencies cause cell irregularity or improper cell performance.
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A endment No. g, J5' 60
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