ML20155F886
| ML20155F886 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 04/11/1986 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20155F890 | List: |
| References | |
| NUDOCS 8604250301 | |
| Download: ML20155F886 (8) | |
Text
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PilRLIC SERVICE ELECTRIC A GAS COMPANY AND ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-354 HOPE CREEK GENERATING STATION EACILITY OPERATING LICENSE License No. NPF-50 1.
The Nuclear Deculatory Commission (the Comission or the NRC) has found that:
A.
The application for a license filed by the Public Service Electric A Gas Company, acting on behalf of itself and Atlantic City Electric Company (the licensees), complies with the standards and reauirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comis-sion's regulations set forth in 10 CFR Chapter I, and all reautred notifications to other agencies or bodies have been duly made; B.
Construction of the Hope Creek Generating Station (the facility) has been substantially completed in conformity with Construction Permit No. CPPR-120 and the application, as amended, the provisions of the Act and the reculations of the Commission; C.
The facility will operate in conformity with the application, as arended, the orovisions of the Act, and the reculations of the Comission (except as exempted from compliarce in Section 7.0. below1; D.
There is reasonable assurance: (i) that the activities authorized by this operatina license can be conducted without endangerina the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's reoulations s9t forth in 10 CFR Chapter I (except as exempted from comoliance in Section P.D.
below);
E.
Public Service Electric & Gas Companv* is technically qualified to engage in the activities authorized by this license in accordance with the Comission's regulations set forth in 10 CFR Chapter I; F.
The licensees have satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Aareements," of the Commission's regulations; G.
The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public;
- Public Service Electric & Gas Company is authorized to act as agent for Atlantic City Electric Company and has exclusive responsibility and control over the ohysical construction, operation and maintenance of the facility.
8604250301 860411 PDR ADOCK 05000354 P
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H.
After weichino the environmental, economic, technical, and other i
benefits of the facility against environmental and other costs and
.considering available alternatives, the issuance of Facility Operating License No. NPF-50, sub.iect to the conditions for protection of the environment set forth in the Environmental Protection Plan attached as Appendix R, is in accordance with 10 CFR Part 51 of the Consnission's reculations and all applicable requirements have been satisfied; and T.
The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will he in accordance with the Consnissinn's regulations in 10 CFR Parts 30, 40 and 70.
2.
Based on the foregoinq findings regarding this facility, Facility Operatino License No. NPF-50 is hereby issued to the Public Service Electric 8 Gas Company and Atlantic City Electric Company (the licensees 1 to read as follows:
A.
This license applies to the Hope Creek Generatino Station, a boiling water nuclear reactor, and associated equipment (the facility) owned by Public Service Electric & Gas Company and Atlantic City Electric Comoany. The facility is located on the licensees' site on the east bank of the Delaware River in Lower Alloways Creek Township, Salem County, New Jersey. The facility is located aporoximatelv etcht miles southwest of Salem, New Jersey and is described in the Public Service Electric 8 Gas Company's Final Safety Analysis Report, as suoniemented and amended, ar.d in the Environmental Report, as supolemented and amended.
B.
Sub,iect to the conditions and requirements incorporated herein, the Commission hereby licenses:
(1) Public Service Electric A Gas Company (PSEAG), pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use and operate the facility at the above designated location in Salem County, New Jersey, in accordance with the procedures and limitations set forth in this license;
(?) Atlantic City Electric Company, pursuant to Section 103 of the Act and 10 CFR Part 50, to possess the facility at the dasignated I
location in Salem County, New Jersey, in accordance with the procedures and limitations set forth in this license; (3) PSE8G, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the. limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; l
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.- (4) PSEAG, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startuo, sealed sources for reactor instrumentation and radiation monitor-ing equipment calibration, and as fission detectors in amounts as required; (5) PSE&G, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as reouired any byproduct, source or special nuclear material without restriction to chemical or physical fom, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) PSEAG, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate. such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This license shall be deemed to contain and is subject to the condi-tions specified in the Comission's regulations set forth in 10 CrR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Comission now nr here-after in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level PSE&G is authorized to operate the facility at reactor core onwer levels not in excess of 3293 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein. Pending Comission approval, this license is restricted to power levels not to exceed five percent of rated oower (164.65 mecawatts thema11 (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the En-vironmental Protection Plan contained in Appendix R. both of which are attached hereto, are hereby incorporated into this license.
PSE&G shell operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
. (3) Turbine System Maintenance Procram ISection 3.5.1.3.3, SER; Section 3.5.1.3.3, SSER No. 5)*
PSE&G shall submit a turbine system maintenance program based on the manufacturer's calculations of missile-generated oroba-bilities by no later than 3 years from the date of this license.
(4) Inservice Testing of Pumps and Valves (Section 3.9.6, SSEP No. 4)
Pursuant to 10 CFR 50.55a and for the reasons set forth in Section 3.9.6 of SSER No. 4, the relief identified in the PSE&r, submittal dated July 12, 1985, recuesting relief from certain pump and valve testing reouirements of 10 CFR 50.55a(o) is oranted, for a period of no lonner than two years from the date of issuance of this license or until a detailed review of the inservice testing program for pumos and valves, has been completed, which-ever comes first.
(5) Envirenmental Oualification (Section 3.11.5, SSED No. 51 a.
Prior to startup following the first refuelina outaae, the qualified life of the electrical couloment under nurchase order M-48 shall be recalculated on the basis of the actual temperatures monitored at the equioment locations durina the first c.vcle of operation, with adequate consideration of maroin.
b.
Prior to achievina initial criticality, the 53 Tobar Model 32, Series 2 transmitters included in the harsh environment oualification program shall be replaced with qualified Rosemount Model 11539 transmitters.
(6) Inservice Inspection (Section 6.6, SERj Sections 5.2.4.3 and 6.6.3, 55ER No. 5)
PSE&G shall submit an inservice inspection program in accordance a.
with 10 CFR 50.55a(g)(4) for staff review within six months of the issuance of this license.
b.
Pursuant to 10 CFR 50.55afa)(3) and for the reasons set forth in Sections 5.2.4.3 and 6.6.3 of SSER No. 5, the relief identified in the PSEAG submittal dated November 18, 1985, as revised by the submitta? dated January 20, 1986, requesting relief from certain requirements of 10 CFR 50.55afg) for the preservice inspection program, is granted.
The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
. (7) Fuel Storage and Handlina (Section 9.1, SSER No. 5) a.
No more than a total of three (3) fuel assemblies shall be out of approved shippino containers or fuel assembly storace racks or the reactor at any one time, b.
The above three (3) fuel assemblies as a group shall maintain a minimum edge-to-edge spacinq of twelve (12) inches from the shioping container array and the storage rack array.
c.
Fresh fuel assemblies, when stored in their shiocinq con-tainers, shall be stacked no more than three (31 containers high.
(81 Fire Protection (Section 9.5.1.8, SSER No. 51 DSE&G shall imolement and maintain in effect all provisions of the approved fire protection proaram as described in the Final Safety Analysis Report for the facility through Amendment No. 13 and as described in submittals dated August I? and 27 November 21 and 29, December 3 and 16, 1985, January 3, and April 8,1986, and as approved in the SER dated October 1984 (and Supplements 1 through
- 5) subject to the following provision:
z The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
(9) Solid Waste Process Control Program (Section 11.4.2. SER; Section 11.4, 55ER No. 4)
PSE8G shall obtain NRC approval of the Class R and C solid waste process control prooram prior to processing Class R and C solid wastes.
(10) Emeroency Plannino (Section 13.3, SSER No. 5)
In the event that the NRC finds that the lack of prooress in completion of the procedures in the Federal Emergency Manacement Agency's final rule, 44 CFR Part 350, is an indicatinn that a ma.ior substantive problem exists in achieving or maintaining an adequate state of emergency preparedness, the provisions of 10 CFR Section 50.54(s)(2) will apply.
(11) Initial Startup Test Program (Section 14, SSER No. 5)
Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month o' such change.
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. (12) Partial Feedwater Heatino (Section 15.1, SER; Section 15.1, 55ER No. 5)
PSE&G shall not operate the facility (other than for normal start-up or shutdown 1 with the feedwater inlet temperature less than 424.5'F.
(13) Detailed Control Room Desion Review (Section 18.1, SSER No.5) a.
PSE8G shall submit for staff review Detailed Control Room Design Review Sumary Reports II and III on a schedule consistent with, and with contents as specified in, its letter of January 9, 1986, b.
Prior to exceeding five percent power, PSE8G shall provide temporary zone markings on safety-related instruments in the control room.
(141 Safety Parameter Disolav System (Section 18.2, SSER No. 51 Prior to restart following the first refueling outage, the licensee shall, per its commitment made in a letter dated March 7, 1986, add the followino parameters to the SPDS and have them operational:
a.
Primary containment radiation b.
Primary containment isolation status c.
Combustible gas concentration in primary contairment d.
Source range neutron flux D.
The facility requires exemotions from certain requirenents of 10 CFR Part 50 and 10 CFR Part 70. An exemption from the criticalitv alarm requirements of 10 CFR 70.24 was granted in Special Nuclear Material License No. 1953, dated Auoust 21, 1985. This exemption is described in Section 9.1 of Supplement No. 5 to the SER. This previously granted exemption is continued in this operating license. Exemptions from certain requirements of Appendix A to 10 CFR Part 50, are described in Supplement No. 5 to the SER. These include (a) a schedular exemption to the requirements of General Desian Criterion 17, permitting delaying completion of preoperational testino of Diesel Generator "D" until prior to initial criticality (Appendix R of SSER 5);- (b) a schedular exemption to the requirements of General Design Criterion 13, permitting delaying completion of preooerational testing of the Traversing incore Probe System until prior to initial criticality (Appendix R of SSER 5); (c) a schedular exemption to the requirements of General Design Criterion 60, permitting delaying completion of preoperational testing of the Offgas System until prior to fully tensioning the reactor pressure vessel head closure bolts (Appendix R of SSER 5); (d) a schedular exemption to the requirements of General
Design Criterion 64, permitting delaying functionality of the Turbine Building Circulating Water System-Radiation Monitoring System until 5 percent power for local indication, and until 120 days after fuel load for control room indication (Appendix P of SSER 5). Exemptions from certain requirements of Appendix J to 10 CFR Part 50, are described in Supplement No. 5 to the SER. These include (a) an exemption from the requirementofParagraphIII.D.2(b)(ii)ofAppendixJ,exemptingoverall containment air lock leakage testing unless maintenance has been per-formed on the air lock that could affect air lock sealing capability (Section 6.2.6 of SSER 5); (b) an exemption from the requirement of Paragraph III.C.2(b) of Appendix J exempting main steam isolation valve leak-rate testing at 1.10 Pa (Section 6.2.6 of SSER 5); (c) an exemption from Paragraph III.D.3 of Appendix J exempting Type C testing on traversing incore probe system shear valves (Section 6.2.6 of SSER 5); (d) an exemption from Paragraph III.D.2(a) of Appendix J, exempting Type C testing for instrument lines and lines containing excess flow check valves (Section 6.2.6 of SSER 5); and (e) an exemption from Paragraph III.C.2(a) of Appendix J, exempting Type C testing of thennal relief valves (Section 6.2.6 of SSER 5). These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security.
These exemptions are hereby granted. The special circumstances regarding each exemption are identified in the referenced section of the safety evaluation report and the supplements thereto. These exemptions are granted pursuant to 10 CFR 50.12. With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.
E.
PSE&G shall fully implement and maintain in effect all provisions of the physical security, guard training and qualification, and safeguards contingency plans previously approved by the Commission and all amend-ments and revisions to such plans made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). These plans, which'contain safeguards information protected under 10 CFR 73.21, are entitled: " Hope Creek Generating Station Security Plan," with revisions submitted through March 20, 1986, " Hope Creek Generating Station Security Training and Qualification Plan," with revisions submitted through July 18, 1984, and " Hope Creek Generating Station Security Contingency Plan," with revisions submitted through July 23, 1985.
F.
Except as otherwise provided in the Technical Specifications or Environmantal Protection Plan, PSE8G shall report any violations of the requirements contained in Section 2.C of this license in the following manner:
initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System with written followup within thirty) days in accordance with the procedures described in 10 CFR 50.73(b, (c), and (e).
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. G.
The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accord-ance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
H.
This license is effective as of the date of issuance and shall expire at midnight on April 11, 2026.
FOR THE NUCLEAR REGULATORY COMMISSION re G
isenhu, Act ng Director Office of uclear Reactor Regulation
Enclosures:
1.
Appendix A - Technical Specifications (NUREG-1186) 2.
Appendix B - Environmental Protection Plan Date'of Issuance: April 11,1986