ML20082Q478
| ML20082Q478 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/05/1991 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | GPU Nuclear Corp, Jersey Central Power & Light Co |
| Shared Package | |
| ML20082Q482 | List: |
| References | |
| DPR-16-A-153 NUDOCS 9109120190 | |
| Download: ML20082Q478 (11) | |
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GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 153 License No. DPR-16 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by GPU Nuclear Corporation, et al.,
(the licensee), dated August 14, 1990, as revised June 18, 1991, 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 faciltty will operate in conformity wit.h the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is re..onable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety ei the public, and (ii) t. hat such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this ameadment 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.
i 9109120190 910905 l
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Accordingly, t he license is amended by changes to the Technical Specitications as indicated in the attachment to this iteense amendment, and paragraph 2.C.(2) of Facility Operating License No. Dl'R-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. 153, 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 issuance, to be implemented within 30 days of issuance.
i FOR THE NUCLEAR REGULATORY COMMISSION
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Joh Y, Stolz, Directo_r Pr ect Directorate {t D ision of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Attachment:
l Changes to the Technical Specifications Date of Issuance: September 5, 1991 r
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ATTACHr1ENT TO LICENSE AMENI)t1ENT NO. 153 l
FACILITY OPERATING LICENSE NO_. DPR-16 DOCKET NO. 50-219 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert Page 3.4-1 Page 3.4-1 3.4-2 3.4-2 3.4-3 3.4-3 3.4-4 3.4-4 3.4-5 3.4-5 3.4-6 3.4-6 3.4-7 3.4-7 3.4-8 1_____._---____
'3.4 EMEPGENCY COOLING Anoticability: Applies to the operating status of the emergency coolant systems.
Obiective To assure operability of the emergency cooling systems.
Stasificati:nn:
A.
C2re Sprav system 1.
The core spray system shall ce operable at all times with irradiated fuel in the reactor vessel, except as otherwise specified in this section.
2.
The absorption chamber water volume shall be at least 82,000 ft.3 in order for the enre spray system to be considered operable.
3.
If one core spray system loop or its core spray header uelta P instrumentation becomes inoperable during the run mode, the reactor may remain in operation for a period not to exceed 7 days provided:
- a. The remaining loop has no inoperable components and is demonstrated daily to be operable and,
- b. The average planar linaar heat generation rate (APLHGR) of all the rods in any fuel assembly, as a function of average planar exposure, at any axial location shall not exceed 90% of the limits given in specification 3.10.A.
The action to bring the core to 90% of the APLHCR Limits must be completed within two hours after the system has been determined to be inoperable.
4.
The reactor may remain in operation for a period not to exceed 15 days if one of the redundant active loop components in the core spray system becomes inoperable during the run mode provided:
- a. In the event of an inoperable core spray booster pump, the other core spray booster pun;p in the loop 14 demonstrated daily to be operable.
- b. In the event of an inoperable core spray main pump, the other core spray main pump in the loop is demonstrated daily to be operable and the APLHGR of all the rods in any fuel assembly, as a function of average planar exposure, at any axial location shall not exceed 90% of the limits given in Specification 3.10 A.
The action to bring the core to 90% of the APLHGR Limita must be completed within two hours after the comportent has been determined to be inoperable.
OYSTER CREEK 3.4-1 Amendment Not ys,153
If two of the redundant active loop components become inoperable, the limits of Specification 3.4.A.3 shall apply.
l S.
During the period when one diesel is inoperable, the core spray equipment connected to the operable diesel shall be operable.
6.
If Specifications 3.4.A.3, 3.4.A.4, and 3.4.A.5 are not met, the reactor shall be placed in the cold shutdown condition.
If the core spray system becomes inoperable, the reactor shall be placed in the cold shutdown condition and no work shall be performed on the reactor or its connected syntems which could result in lowering the reactor water level to less than 4'8" above the top of the active fuel.
7.
If necessary to accomplish maintenance or modifications to the core spray systems, their power supplies or water supplier, reduced system availability is permitted when the reactor ist (a) maintained in the cold shutdown condition or (b) in the refuel mode with the reactor coolant syutom maintained at less than 212 F and vented, and (c) no work is performed on the reactor vessel and connected systems that could result in lowering the reactor water level to less than 4'8" above the top cf the active fuel.
Reduced Core Spray System Availability is minimally defined as follows:
a.
At least one core spray pump, and system componente necessary to deliver rated core spray to the reactor vessel, must remain operable to the extent that the pump and any necessary valves can be started or operated from the control room or from local control stations.
b.
The fire protection system is operable, and c.
These systems are demonstrated to be operable on a weekly basis.
8.
If necessary to accomplish maintenance or modifications to the core spray systems, their power supplies or water supplies, reduced system availability is permitted when the reactor is in the refuel mode with the reactor coolant system maintained at less than 212 F or in the startup mode for the purposes of low power physics testing. Reduced core spray system availability is defined as follows:
a.
At least one core spray pump in each loop, and system components necessary to deliver rated core opray to the reactor vessel, must remain operable to the extent that the pump and any necessary valves in each loop can be started or operated from the control room or from local control stations.
b.
The fire protection system is operable and, c.
Each core spray pump and all components in 3.4.A.8a are demonstrated to be operable every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
g OYSTER CREEK 3.4-2 Amendment No.:
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9.
If Specifications 3.4.A.7 and 3.4.A.8 cannot be met, the requirements of Specification 3.4.A.6 will be met and work will be initiated to meet minimum cperability requirements of 3.4.A.7 and 3.4.A.8.
10.
The core spray system is not required to be oporable when the following conditions arr a.
The reactor mode switch is locked in the " refuel" or
" shutdown" position.
b.
(1) There is an operable flow path capable of taking suction from the condensate storage tank and transferring water to the reactor vessel, and (2) The fire protection system is operable, c.
The reactor coolant system is maintained at less than 212 F nnd vented (except during reactor vessel pressure testing).
d.
At least one core spray pump, and system components necessary to deliver rated core spray flow to the reactor vessel, must remain operable to the extent that the pump and any necessary valves can be started or operated from the control room or from local control stations, and the torus is mechanically intact.
e.
(1) No work shall be 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 and the condensate storage tank level is greater than thirty (30) feet (360,000 gallons).
At least two redundant systems including core spray pumps and system components must remain operab3e as defined in d. above OR (2) The reactor vessel head, fuel pool gate, and separator-dryer pool gates are removed and the water level is above elevation 117 feet.
NOTE: When filling the reactor cavity from the condensate storage tank and draining the reactor cavity to the condensate storage tank, the 30 foot limit does not apply provided there is sufficient amount of water to complete the flooding operation.
B.
Automatic Deoressurization System 1.
Five electromatic relief valves of the automatic depressurization system shall be operable when the reactor water temperature is greater than 212 F and pressurized above 110 peig, except as specified in 3.4.B.2.
The automatic pressure relief function of these valves (but not the OYSTER CREEK 3.4-3 Amendment No.: 75,
120,153
automatic depressurization function) may be ir. operable or bypassed during the cystem hydrostatic pressure test required by ASME Code Section XI, IS-500 at or near the end of each ten year inspection interval.
2.
If at any time there are only four operable electromatic relief valves, the reactor may remain in operation for a period not to exceed 3 days provided the motor operated isolation and condensate makeup valves in both isolation condensers are demonstrated daily to be operable.
3.
If Specifications 3.4.B.1 and 3.4.B.2 are not n.et; reactor pressure shall be reduced to 110 psig or less, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.
The time delay set point for initiation after coincidence of low-low-low reactor water level and high drywell pressure shall be set not to exceed two minutes.
C.
Containment Sorav System and Emeroency Service Water System 1.
The centainment spray system and the emergency service water system shall be operable at all times with irradiated fuel in the reactor vessel, except as specified in Specifications 3.4.C.3, 3.4.C.4, 3.4.C.6 and 3.4.C.8.
be less than The absorgtion chamber water volume shall not 2.
82,000 ft in order for the containment spray and emergency service water system to be considered operable.
3.
If one emergency service water system loop becomes inoperable, its associated containment spray system loop shall be considered inoperable.
If one centainment spray system loop and/or its associated emergency service water system loop becomes inoperable during the run mode, the reactor may remain in operation ter a period not to excaed 7 days provided the remaining containment spray system loop and its associated emergency service water system loop each have no inoperable components and are demonstrated daily to be operable.
4.
If a pump in the containment spray system or emergency service water system becomes inoperable, the reactor may remain in operation for a period not to exceed 15 days provided the other similar pump is demonstrated daily to be operable.
A maximum of two pumps may be inoperable provided the two pumps are not in the came loop.
If more than two pumps become inoperable, the limits of Specification 3.4.C.3 shall apply.
5.
During the period when one diesel is inoperable, the containment spray loop and emergency service water system loop connected to the operable diesel shall have no inoperable components.
6.
If primary containment integrity is not required (see Specification 3.5.A), the containment spray system may be made inoperable.
OYSTER CREEK 3.4-4 Amendment No.:
A
-7 If Specifications 3.4 C.~3, 3.4.C.4, 3.4.C.5 or 3.4.C.6 are not-met, thu reactor shall be placed in cold-shutdown condition.
If the col.tainment epray system or the emergency service water system'becomas inoperable, the reactor shall be_placed in the cold shutdown condition and no work shall-be performed on the reactor or its connected systers which could result in lowering the reactor water level to less than 4'8" anove the top of the active' fuel.
'8.
The containment spray system may be made inoperable during the
.ategrated primary centainment leakage rate test required by Specification 4.5, provided that the reactor is maintained in the cold shutdown condition and that no work is performed on the reactor or ite connected systems which could result in lowering the reactor level to less than 4'8" above the cop of
.the active fuel.
D. ' Control Rod Drive Hydraulic Svetem 1.
The control rod drive- (CRD) ' hydraul tc system shall be operable
.when the reactor water temperature is above 212 F except as specified in 3.4.D.7 and 3.4.D.3 below.
2.-
If one CRD hydraulic pump becomes inoperable when the. reactor water temperature is above 212*F, the reactor may remain in operation for a period not to exceed 7 days provided the second CRD hydraulic pump is operating and is checked at-least once every.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />..If this condition cannot be met, the reactor water temperature shall be reduced to less then 212*F.
3.
During reactor vessel pressure testing, at least one CRD pump shall be operable.
E.: Core Sorav and Containment Sorav Pumo Comoartments Doors The core spray _and containment spray pump compartments doors shall be closed at all times except during passage in= order to consider the core spray system and the containment spray system operable.
F.
Fire Protection System 1.
The fire protection system shall be operable at all times with fuel in the reactor vessel except as specified in Specification 3.4.F.2.
2.
If the fire protection system becomes inoperable during the run mode, the reactor may remain in operation provided both core spray system loops are operable with no inoperable components.
Bases:
This specification assures operability of the emergoney core cooling system to provide adequate core cooling. The Oyster Creek ECCS has two core spray loops; each containing a core spray sparger, two main pumpo and two booster pumps.
Specification 3.4.A.1 insures the availability of OYSTER CREEK-3.4-5 Amendment No.: 75 120,153,
core coolingato meet the ECCS acceptance criteria in 10CFR50.46 utilizing the.KAPLHCR limits provided in Section 3.10.
These limits are from calculatione51) thht : include models and procedures which are specified in lOCTRSO Appendix K.
A core spray flow of at least 3400 gpm (1 main and 1 booster pump) from 1 loop plus 2200 gpm (1 main pump) from the other loop 7,
at a vessel pressure of 110 psig is used in the calculation.- Core spray-laop 2 would'be required to deliver 3640 gpm if loop 2 is relied upon as the twu pump contributor and 2360 gpm if loop 2 is the single pump contributor, since loop 2 has flow lesses through cracks in the core spray sparger.
Specification 3.4.A.3 allows continued operation with one core spray loop
- inoperable for a-limited period of time.
An evaluation of cata presented in ReferAnce 5 shows that flow from a single core spray sparger, main and
' booster. pumps delivering 3400 gpm (3640 gpm for loep 2) at a vessel pressure of llo psig, will meet 10 CFR 50.46 criteria with a 10% reduction in MAPLHGR Limits specified in Section 3.10.
At 90% of the APLHGR, each core. spray system is capable of supplying the required minimum bundle flow rate to ensure-core cooling (References 6 and 7). Two hours is allowed for l
a reduction in the APLHCR-limit which is consistent with two hours provided j
by~ipecification 3.10.A.3 to return an exceeded APLHGR to within the prescribed limit.
i Unds.r the operational constraints of Specification 3.4.A.3 the operable core spray loop meets all. Appendix K. requirements except for the case of a
-t core spray line break inside the drywell in the operable loop.
As a result, reactor operation is permitted for a period not to exceed seven j
days. The allowed time out of service for the redundant core spray loop is
. justified based on the low probability of the event, the direct operator
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indication of a Core Spray System pipe break, and emergency procedures
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which provide for additional cooling water through the fire system.
I
' The probabil y of a pipe break between the reactor vessel and the core spray check valve in the operable core spray loop (approx. 28 feet of.6 I
inch pipet compared to the total pipe in the reactor coolant pressure-l boundary is very small. The probability of a core spray line break in conjunction with-the other core spray loop out of service, which in itself
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is a low probability, is so small that it does not constitute an
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unacceptable risk.
In the extremely unlikely event that this LOCA scenario were to occur, the operators are provided with a specific visual and
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- audible alarm alerting them-of a " Core Spray; System I (II) Pipe Breaka (one for each core spray loop).
These alarms are initiated by differential y
pressure detectors on'each core spray loop.
In such a case the core spray-
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line break would occur above the top of the active fuel cllowing the core
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to be re-flooded from the fire protection system through the intact core spray loer.
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. In addition, a small break LOCA in the operable core spray loop prior to a
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larger break will be detected by the drywell unidentified leakage system (drywell sump) even before it is detected by the core spray alarm system.
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Thio will provide the operators with additional time to respond.
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Therefore, the out-of-service time for one of the two core spray loops, as l-
- evaluated as per the guidelines in Reference 8, has been conservatively
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selected to be 7 days.
OYSTER CREEK 3.4-6 Amendment No.:
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.u specification.3.4.A 4 allows continued operation with one component inoperable;for a-limited period of time..
Each core spray loop contains redundant active components based upon Reference 1 or 5, as appropriate.
Therefore, with the loss of one of these components, the system as a whole (both loops) can tolerate an additional single failure of one of its active components and still perform the intended function and meet 10CFR50.46 criteria.
If a redundant active component fails, a fifteen day period is allowed for repairs, based on 1 out of 4 components being required.
3.4.A.4.b insures that the 1 out of 4 requirement is maintained.
Specification 3.4.A.5 ensures that if one diesel is out of service for repair, the core spray. components fed by the other diesel must be operable. Since each diesel will provide power to components for both core-spray loops, the required flow specified in the bases for Specification 3.1.A.1 will be met.
When the reactor is in the shutdown or refueling mode and the reactor coolant system is lees than 212'F and vented and no work is buing performed that could result in lowering the water level to less than 4'8" above the core, the likelihood of a leak or rupture leading to uncovering of the core is very low.
The only source of energy that must_be removed is decay heat and one day after shutdown this-heat generation rate is conservatively calculated to be not more than 0.6% of rated power.
Sufficient core spray flow to cool the core esn be supplied by one core spray pump or one of the two fire protection system pumps under these conditions.
When it is necessary to perform repairs on the core spray syntom components, power supplies or water sources, Specification 3.4.A 7 permits reduced cooling system capability to that which could provide sufficient core spray flow from two independent sources.
Manual initiation of these systems is adequate since it can be easily accomplished within 15 minutes during which time the temperature rise in the reactor will not reach 2200*F.
l l
In order to allow for certain primary system maintenance, which will include control rod drive repair, LPRM removal / installation, reactor leak test,:etc., (all performed according to approved procedure), Specification 3.4.A.B requires the-availability of an additional core spray pump-in an independent loop, while this maintenance is being performed the likelihood of'the core being uncovered is still considered to be very low,.however, j
the requirement of a second core spray pump capable of full rated flow and
-the 72; hoar operability demonstration of both core spray pumps is l
.specified.
Specification 3.4.A.10 allows the core spray system to be inoperable in the cold shutdown or refuel modes if the reactor cavity is flooded and the spent fuel pool gates are removed and a source of water supply to the reactor vessel is available.
Water would then be available to keep the core flooded.
'The relief valves of the automatic depressurization system enable the core spray system to provide protection against the small break in the event the l
feedwater system is not active.
L OYSTER CREEK 3.4-7 Amendment No.: >f 158 1
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4.
- The containment spray system is provided to remove heat energy from the containment-in the event of a loss-of-coolant accident.
The flow from one pump in either-loop'is more than ample to provide the required heat removal
-capability (2).-
The emergency service water. system provides cooling te the containment spray heat exchangers and, therefore, ic required to provide the ultimate heat sink for the energy release in the event of a loss-of-coolant accident.
The emergency service water pumping requirements are those which correspond to containment cooling heat exchanger performance implicit in the containment cooling description.
Since the loss-of-coolant accident while in the cold shutdown condition would not require containment spray, the system may be deactivated to permit integrated. leak rate testing of the primary containment while the reactor is in the cold shutdown condition.
The control rod drive hydraulic system can provide high pressure coolant injection capability.
For break sizes up to 0.002 ft',
a single control rod drive pump with a flow of 110 gpm is adequate for maintaining the water level nearly five feet above the core, thus alleviating the necessity for auto-relief actuation (3).
The core. spray main pump compartments and containment spray pump compartments were provided with water-tight doors (4).
Specification 3.4.E ensures that the doors are in place to perform their intended function.
Similarly, since a loss-of-coolant accident when primary containment integrity is not being maintained would not result in pressure build-up in the drywell or torus, the system may be made inoperable under these conditions. This prevents possible personnel injury associated with contact with chromated torus water, i
References 9
.l.
NEDC-31462P, " Oyster Creek Nuclear Generating Station SAFER /CORECOOL/GESTR-LOCA Loss-of-Coolant Accident Analysis," August 1987.
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2,-
Licensing Application, Amendment 32, Question 3 3.
Licensing Application, Amendment 18, Question 1 j
4.
Licensing Application, Amendment 18, Question 4 l
- 5. 'GPUN Topical Report 053, " Thermal Limits with One Core Spray Sparger" December 1988.
j 6..
NEDE-30010A, " Performance Evaluation of the Oyster Creek Core Spray Sparger", January 1984.
7.
Letter and enclosed Safety Evaluation, Walter A. Paulson (NRC) to P.
B.
I FiedlerE(GPUN), July 20, 1984.
l 8.
APED-5736, " Guidelines for Determining Safe Test Intervals and Repair Times
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for Engineered Safeguards", April 1969.
I OYSTER CREEK 3.4-8 Amendment No.: 153 l
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