ML20199C253
| ML20199C253 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 11/06/1997 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Public Service Electric & Gas Co, Atlantic City Electric Co |
| Shared Package | |
| ML20199C257 | List: |
| References | |
| NPF-57-A-110 NUDOCS 9711190280 | |
| Download: ML20199C253 (7) | |
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en:gb UNITED STATES -
f NUCLEAR REGULATORY COMMISSION wAswiwovow, n.c. soses.aooi PUBLIC SERVICE ELECTRIC & GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-354
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HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE' Amendment No.110 License No. NPF-57 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company (PSE&G) dated August 20, 1997, 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:
(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 Commission's regulations set forth in 10 CFR. Chapter I; i
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.
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:
N NM54 PDR e
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. (2) Technical Snecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.110, 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.
In addition, paragrenh 2.C.(14) to Facility Operating License No. NPF-57 is amended as follows:
(14) Additionki Conditions.
The Additional Conditions contained in Appendix C, as revised
-through Amendment No. 110, are hereby incorporated into this license.
Public Service Electric and Gas Company shall operate the facility in accordance with the Additional Conditions.
3.
The license amendment is effective as of its date of issuance and shall-be implemented within 60 days.
Implementation of this amendment shall include the relocation of the suppression cnamber water volume, as contained in Technical Specifications 3.5.3.a. 3.5.3.b, 3.6.7.1.a.1 and 5.2.1 to the Updated Final Safety Analysis Report, as described in the licensee's application dated August 20, 1997, and evaluated in the staff's safety evaluation attached to this amendment' FOR THE NUCLEAR REGULATORY COMMISSION Jph
. Stolz, irector o ect Directorate I ision of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachments:- 1.
Page 1 to Appendix C of License
- No. NPF-57 2.
Changes to the Technical Specifications Date of Issuance: November 6, 1997 i
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- Page 1 to Appendix C is attached, for convenience, for the composite license to reflect this change.
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ATTACHMENT TO LICENSE AMENDMENT NO. 110 FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 t
1.
Insert Appendix C, Page 1 2.
Replace the following pages of th? Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amandment number and contain vertical lines indicating the area of change.
Remove Insert 3/4 5-8 3/4 5-8 3/4 6-12 3/4 6-12 5-1 5-1 I
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APPENDIX C ADDITIONAL CONDITIONS OPERATING LICENSE NO. DPR-51 Public Service Electric and Gas Compcny anj Atlantic City Electric Company shall comply with the following conditions on the schedules noted below:
Amendment Additional Condition Implementation Number Date 97 The licensee is authorized to relocate certain The amendment Technical Specification requirements to shall be licensee-controlled documents.
Implementation implemented of this amendment shall include the relocation within 60 days of these technical specification requirements from March 21, to the appropriate documents, as described in 1997.
the licensee's application dated January 11, 1996, as supplemented by letters dated February 20 Hay 22, June 27, July 12 Dr:cember 23, 1996, and March 17, 1997, and avaluated in the staff's safety evaluation attached to this amendment.
103 The licenses shall relocate tSe list The amendment of " Motor Operated Valves - 1hermal Overload shall be Protection (BYPASSED)" from the Tcchnical implemented Specifications (Table 3.8.4.2-1) described into the Updated within 50 days Final Safety Analysis Report, as from September 16, the license s application dated July 7, 1997, 1997 and evaluated in the staff's safety evaluation attached to this amendment.
105 The licensee shall use the Banked The amendment Pattern Withdrawal System or an improved shall be version such as tha Reduced Notch Worth implemented Procedure as described in the licensee's within 60 days applicatio-dated June 19, 1997, and from September 30, evaluated ti. the staff's safety evaluation 1997 attached to this amendment.
110 The licensee shall relocats the suppression The amendment I
chamber water volume, as contained in shall be Technical Specifications 3.5.3.a. 3.5.3.b, implemented 3.6.2.1.a.1 and 5.2.1 to the Updated Final within 60 days Safety Analysis Report, as described in the from November 6, licensee's application dated August 20, 1997 1997, and evaluated in the staff's safety evaluation attached to this amendment.
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i EMERGENCY CORE COOLING LYSTEMS j
1 3/4.6.3 SUPPRESSION CHAMDER LIMITING CONDITION FOR OPERATION i
3.5.3 The suppression chamber shall be OPERABLE:
a.
In OPERATIONAL CONDITION 1, 2 and 3 with an indicated water level of at least 74.5*.
b.
In OPERATIONAL CONDITION 4 and 5' with an indicated water level of at least 5.0" except that the suppression chamber level may be less than the limit or may be drained provided that:
1.
No operations are performed that have a potwntial for draining the reactor vessel, 2.
The reactor mode switch is locked in the Shutdown or Refuel
- position, 3.
The condensate storage tank contains at least 135,000 available gallone of water, and 4.
The core spray system is OPERABLE per Specification 3.5.2 with an OPERABLE flow path capable of taking suction from the condenrate storage tank and transferring the water through the spray sparger to the reactor vessel.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2,
3, 4 and 5*.
hCTION:
a.
In OPERATIONAL CONDITION 1, 2 or 3 with the suppression chamber water level less than the above limit, restore the water level to within the limit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 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.
In OPERATIONAL CONDITION 4 or 5* with the suppression chamber water level less than the above limit or drained and the above required conditions not satisfied, suspend CORE ALTERATIONS and all
. operations that have a potential for draining the reactor vessel and lock the reactor mode switch in the Shotdown position. Establish SECONDARY CONTAINWFT INTEGRITY within 8 Fours.
- The suppression cha aber is not required to be OPERABLE provided that the reactor vessel head 's removed, the cavity is flooded or being flooded from the suppression pool, the spent fuel pool gates are removed when the cavity is flooded, and the water level is maintained within the limits of-Specifications 3.9.8 and 3.9.9.
HOPE CREEK 3/4 5-8 Amendment No. 110
CONTAINMENT SYSIEtig 3 /4. 6,2 DEPREjSURIZATION 9YSTEMS SUPPRE9SION CHAMBEB LIMITING CONDITION FOR OPERATION
-3.6.2.1 The suppression chamber shall be OPERABLE withs a.
The pool water:
1.
With an indicated water level between 74.5a and 7 8. 5 a and a l
2.
Maximum average temperature of 95*F during OPERATIONAL CONDITION 1 or 2, except that the maximum everage temperature nmy be permitted to increase to a) los*F during testing which adds heat to the suppression chamber.
b) 110*F with THERMAL POWER less than or equal to 1% of RATED THERMAL POWER.
3.
Maximum average temperature of 95'F during OPERATIONAL CONDITION 3, except that the maximum average tet.perature may be permitted to increase to 120*F with the main steam line isolation valves closed following a scram, b.
A total leakage between the suppression chamber and drywell of less than the equivalent leakage through a 1-inch diameter orifice at a differential pressure of 0.80 psig.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and P.
ACTION:
a.
With the suppression chamber water level outside the above limits, restore the water level to within the limits within 1 hout 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 withs.1 the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
With the suppression chamber average water temperature greater than 95'F and THERMAL POWER greater than 1% of RATED THERMAL POWER, restore the average temperature to less than or equal to 95'F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-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 />, except, as permitte.d above:
1.
With the suppression chamber average water temperature greater than 105'F during testing which adds heat to the suppression chamber, stop all testing which adds heat to the suppression chamber and restore the average temperature to less than 95*
within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be f r. at lear.t 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 />.
2.
With the suppression chamber average water temperature greater than 110*F, place the reactor mode switch in the Shutdown position and operate at least one residual heat removal loop in the suppression pool cooling mode.
HOPE CREEK 3/4 6-12 Amendment No. 110
5.0 DES!GN FEATURES
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5.1 SITE EXCLUS70N AREA AND MAP DEFINING UNRESTRICTED ARMS AND SITE BOUNDARY FOR RADICACTIVE GASEOUS AND LIOUID EFFLUENTS 5.1.1 The exclusion area shall be as Jhown in Figure 5.1.1-1. Information regardir.g radioactive gaseous and liquid effluents which will allow identification of structures and release pointe as well as definition of i
UNRESTRICTED AREAS within the SITE BOUNDARY that are accessible to MEMBERS OF THE PUBLIC, shall be as shown in Figure 5.1.1-1.
LOW POPULATION ZONE 5.1.2 The low population zone shall be as shown in Figure 5.1.2-1. The circle with the five mile radius is the low population zone.
5.2 CONTAINMENT CONFIGURATION 5.2.1 The primary containment is a steel structure composed of a spherical lower portion, a cylindrical middle portion, and a hemispherical top head which form a drywell. The drywell is attacted to the suppression chamber through a series of downcomer vents. The suppression chamber is a steel pressure vessel in the shape of a torus. The drywell has a nominal free air volume of 169,000 cubic feet. The suppression chamber has an air volume of 137,000 cubic feet and a water region as described in Technical Specification Bases 3/4.6.2, Depressurization Systems.
DESIGN TEMPERATURE AND PRESSURE 5.2.2 The primary containment is designed and shall be maintained for a.
Maximum internal pressure 62 psig.
b.
Maximum internal temperatures drywell 340'F.
suppression pool 310'F.
c.
Maximum external differential pressure 3 paid.
SECONDARY CONTAINMENT 5.2.3 The secondary containment consists o.
the Reactor Building, and a portion of the main steam tunnel and has a tree volume of 4,000,000 cubic feet.
1 HOPE CREEK 5-1 Amendment No.110
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