ML20100J087
| ML20100J087 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 02/26/1996 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Public Service Electric & Gas Co, Atlantic City Electric Co |
| Shared Package | |
| ML20100J092 | List: |
| References | |
| NPF-57-A-094 NUDOCS 9602280234 | |
| Download: ML20100J087 (7) | |
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f f-I*g UNITED STATES NUCLEAR REGULATORY COMMISSION I*
f WASHINGTON, D.C. 20066-0001
.....,o PUBLIC SERVICE ELECTRIC & GAS C0f1PANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 94 License No. NPF-57 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric
& Gas Company (PSE&G) dated February 5, 1996, as supplemented by letter dated February 14, 1996, 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 operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance:
(1) 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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon 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.
2.
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 Facility Operating License No. NPF-57 is hereby amended to read as follows:
9602280234 960226 PDR ADOCK 05000354 p
(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 94, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into the license.
PSE&G shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance, and shall be implemented within 3 days.
FOR THE NUCLEAR REGULATORY COMMISSION-
,MIts
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Jo F. Stolz, Directorf ject Directorate I-Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 26, 1996 I
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ATTACHMENT TO LICENSE AMENDMENT NO. 44 FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 3/4 6-15 3/4 6-15 3/4 6-16 3/4 6-16 B 3/4 6-4 B 3/4 6-4 B 3/4 6-4a
CONTAINMENT SYSTEMS SUPPRESSION POOL SPRAY LIMITING CONDITION FOR OPERATION 3.6.2.2 The suppression pool spray mode of the residual heat removal (RHR) system shall be OPERABLE with two independent loops, each loop consisting of:
a.
An OPERABLE flow path capable of recirculating water from the suppression chamber through an RHR heat exchanger and the suppression pool spray sparger.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.
ACTION:
a.
With one suppression pool spray loop inoperable, restore the inoperable loop to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
With both suppression pool spray loops inoperable, restore at least one loop to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN
- within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.2.2 The suppression pool spray mode of the RHR system shall be demonstrated OPERABLE:
i a.
At least once per 31 days by verifying that each valve, manual, power operated or automatic, in the flow path that is not locked, sealed or otherwise secured in position, is in its correct 4
position.
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b.
By verifying that each of the required RHR pumps develops a flow of at least 500 gpm on recirculation flow through the RHR heat exchanger, its associated closed bypass valve, and suppression
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pool spray sparger when tested pursuant to Specification 4.0.5.
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- Whenever both RHR subsystems are inoperable, if unable to attain COLD SHUTDOWN as required by this ACTION, maintain reactor coolant temperature as low as practical by use of alternate heat removal methods.
EOPE CREEK 3/4 6-15 Amendment No. g4
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CONTAINMENT SYSTEMS l
l SUPPRESSION POOL COOLIf7G LIMITING CONDITION FOR OPERATION i
I 3.6.2.3 The suppression pool cooling mode of the residual heat removal (RHR) i system shall be OPERABLE with two independent loops, each loop consisting of:
a.
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b.
An OPERABLE flow path capable of recirculating water from the
-suppression chamber through an RHR heat exchanger.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.
ACTION:
a.
With one suppression pool cooling loop inoperable, restore the inoperable loop to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
With both suppression pool cooling loops inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN
- within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.2.3 The suppression pool cooling mode of the RHR system shall be demonstrated OPERABLE:
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a '.
At least once per 31 days by verifying that each valve, manual, power operated or automatic, in the flow path that is not locked, 4
sealed or otherwise secured in position, is in its correct position.
b.
By verifying that each of the required RHR pumps develops a flow of at least 10,000 gpm on recirculation flow through the RHR heat exchanger, its associated closed bypass valve, and the suppression pool when tested pursuant to Specification 4.0.5.
- Whenever both RHR subsystems are inoperable, if unable to attain COLD JHUTDOWN as required by this ACTION, maintain reactor coolant temperature as low as practical by use of alternate heat removal methods.
HOPE CREEK 3/4 6-16 Amendment No g4
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e CONTAINMENT SYSTEMS BASES DEPRESSURIZATION SYSTEMS (Continued) tested during the Humboldt Bay and Bodega Bay tests was 170*F and this is conservatively taken to be the limit for complete condensation of the reactor coolant, oithough condensation would occur for temperatures above 170*F.
Should it be necessary to make the suppression chamber inoperable, this shall only be done as specified in Specification 3.5.3.
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The Hope Creek design contains'a bypass line around each of the RHR heat i
exchangers. The line contains a valve that is used for adjusting flow through the heat exchanger.
The valve is not designed to be a tight shut-off valve.
j With the bypass valve closed, a portion of the total flow travels through the bypass line, which can affect overall heat transfer, although no heat transfer performance requirement of the heat exchanger is intended by the Technical Specification RHR pump Surveillance Requirements.
One of the Surveillance Requirements for the Suppression Pool Cooling (SPC) and Suppression Pool Spray (SPS) modes of the RHR system demonstrate that each RHR pump develops the required flowrate while operating in the applicable mode with flow through the associated heat exchanger and its closed bypass valve. Verifying that each RHR pump develops the required flow rate, wh13e operating in the applicable mode with flow through the heat exchanger and its associated closed bypass valve, ensures that pump performance has not
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degnaded during the cycle.
Flow is a normal test of centrifugal pump performance required by ASME Code,Section XI.
This test confirms one point on the pump baseline curve and is indicative of overall performance.
Such j
inservice inspections confirm component OPERABILITY, trend performance, and detect incipient failures by indicating abnormal performance.
l Under full power operating conditions, blowdown from an initial suppression chamber water temperature of 95'F results in a water temperature of approximately 135'F immediately following blowdown which is below the 200'F j
used for complete condensation via mitered T-quencher devices. At this temperature and atmospheric pressure, the available NPSH exceeds that required by both the RHR and core spray pumps, thus there is no dependency on containment overpressure during the accident injection phase. If both RHR loops are used for containment cooling, there is no dependency on containment overpressure for post-LOCA operations.
a Experimental data indicates that excessive steam condensing loads can be avoided if the peak local temperature of the suppression pool is maintained below 200*F during any period of relief valve operation. Specifications have been placed on the envelope of reactor operating conditions so that the reactor can be depressurized in a timely manner to avoid *'
regime of potentially high suppression chamber loadings.
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HOPE CREEK B 3/4 6-4 Amendment No. 94 6
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'faNTAINMENT SYSTEMS
.j BASES DEPRESSURIZATION SYSTEMS (Continued)
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Because of the large volume and thermal capacity of the suppression pool, the volume and temperature normally changes very slowly and monitoring these parameters daily is sufficient to establish any temperature trends. By requiring the suppression pool temperature to be frequently recorded during periods of significant heat addition, the temperature trends will be closely followed so that appropriate action can be taken. The requirement for an external visual examination following any event where potentially high loadings could occur provides assurance that no significant damage was encountered. Particular attention should be focused on structural discontinuities in the vicinity of the relief valve discharge since these are expected to be the points of highest stress.
l In addition to the limits on. temperature of the suppression chamber pool water, operating procedures define the action to be taken in the event a safety-relief valve inadvertently opens or sticks open. As a minimum this action shall includes (1) use of all available means to close the valve, (2) initiate suppression pool water cooling, (3) initiate reactor shutdown, and (4) if other safety-relief valves are used to depressurize the reactor, their discharge shall be' separated from that of the stuck-open safety relief valve to assure mixing and uniformity of energy insertion to the pool.
i In conjunction with the Mark I containment Long Term Program, a plant unique analysis was performed which demonstrated that the containment, the attached piping and internal structures meet the applicable structural and mechanical acceptance criteria for Hope Creek. The evaluation followed the design basis loads defined in the Mark I Load Definition Report, NEDO-21888, December 1978, as modified by NRC SER NUREG 0661, July 1980 and Supplement 1, 1
j August 1982, to ensure that hydrodynamic loads, appropriate for the life of j
the plant, were applied.
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HOPE CREEK B 3/4 6-4a Amendment No.g i
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