ML20205E950
| ML20205E950 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 07/25/1986 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205E954 | List: |
| References | |
| NUDOCS 8608190042 | |
| Download: ML20205E950 (44) | |
Text
\\
UNITED STATEF 8
NUCLEAR REGULATERY COMMISSION g
r, a
WASHINGTON, D. C. 20065
\\*****/
PUBLIC SERVICE ELECTRIC & GAS COMPANY AND ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-354 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE License No. NPF-57 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for a license filed by the Public Service Electric &
Gas Company, acting on behalf of itself and Atlantic City Electric Company (the licensees), complies with the standards and requirements 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 required 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 Pemit No. CPPR-120 and the application, as amended, the provisions of the Act and the regulations of the Comission; C.
The facility will operate in confonnity with the application, as amended, the provisions of the Act, and the regulations of the Comission (except as exempted from compliance in Section 2.D. below);
D.
There is reasonable assurance: (1) that the activities authorized by this operating license 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 (except as exempted from compliance in Section 2.D.
below);
E.
Public Service Electric & Gas Company
- 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 It F.
The licensees have satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements," of the Comission'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 physical construction, operation and maintenance of the facility.
0600190042 060725 DR ADOCK 0500 4
4.
H.
After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of Facility Operating License No. NPF-57, sub,iect to the conditions for protection of the environment set forth in the Environmental Protection Plan attached as Appendix B, is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and I.
The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40 and 70.
2.
Based on the foregoing findings and approval by the Nuclear Regulatory Commission at a meeting on July 21, 1986, the License for Fuel Loading and low Power Testing, license No. NPF-50, issued on April 11, 1986, is super-seded by Facility Operating License NPF-57 hereby issued to Public Service Electric & Gas Company and Atlantic City Electric Company (the licensees),
to read as follows:
A.
This license applies to the Hope Creek Generatina Station, a boiling water nuclear reactor, and associated equipment (the facilityl owned by Public Service Electric & Gas Company and Atlantic City Electric Company. The facility is' located on the licensees' site on the east bank of the Delaware River in Lower A110 ways Creek Township, Salem County, New Jersey. The facility is located approximately eight miles southwest of Salem, New Jersey and is described in the Public Service Electric & Gas Company's Final Safety Analysis Report, as supplemented and amended, and in the Environmental Report, as supplemented and amended.
i B.
Subject to the conditions and requirements incorporated herein, the l
Commission hereby licenses:
(1)
Public Service Electric & Gas Company (PSE&G), 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; (2)
Atlantic City Electric Company, pursuant to Section 103 of the Act and 10 CFR Part 50, to possess the facility at the designated I
location in Salem County, New Jersey, in accordance with the procedures and limitations set forth in this license; (3)
PSE&G, 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 reouired for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended;
. ~ - -, - - - - -,, -. -, - - -, -
- (4)
PSE8G, 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 nuc] ear material as sealed neutron sources for reactor startup, 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 required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6)
PSE&G, 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 conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is sub,iect to all applicable provisions of the Act and to the rules, regulations and orders of the Comission now or hereafter in-effect; and is sub,iect to the additional conditions specified or incorporated below:
(1)
Maximum Power level PSE&G is authorized to operate the facility at reactor core power l
1evels not in excess of 3293 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the En-vironmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.
PSE&G shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Inservice Testina of Pumps and Valves (Section 3.9.6, SSER 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&G submittal dated July 12, 1985, requesting relief from certain pumo and valve testing requirements of 10 CFR 50.55a(g) is granted, until April 11, 1988, or until a detailed review of the inservice testing program for pumps and valves has been completed, whichever comes first.
- 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.
4 (4)
Inservice Inspection (Section 6.6, SER; Sections 5.2.4.3 and 6.6.3, 55ER No. 5)
_g.,PSE&G shall submit an inservice inspection program in accordance with 10 CFR 50.55a(g)(4) for staff review by October 11, 1986.
b.
Pursuant to 10 CFR 50.55a(a)(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 PSE8G submittal dated November 18,1985, as revised by the submittal dated January 20, 1986, requesting relief from certain requirements of 10 CFR 50.55a(g) for the preservice inspection program, is granted.
(5)
Solid State Logic Modules (Section 7.3.2.5, SSER No. 6)
PSE&G shall implement a reliability program, to demonstrate solid state logic module reliability, as described in its letters dated June 13 and 24, 1986. The results of the reliability program shall be submitted to the staff prior to the end of the first refueling outage.
(6)
Fuel Storage and Handling (Section 9.1, SSER No. 51 a.
No more than a total of three (3) fuel assemblies shall be out of approved shipping containers or fuel assembly storage 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 spacing of twelve (12) inches from the shipping container array and the storace rack array, c.
Fresh fuel assemblies, when stored in their shipping con-tainers, shall be stacked no more than three (3) containers high.
1 (7)
Fire Protection (Section 9.5.1.8, SSER No. 5; Section 9.5.1, 55ER No. 6)
PSE&G shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility through Amendment No. 15 and as described in its submittal dated May 13, 1986, and as approved in the SER dated October 1984 (and Supplements 1 through 6) sub.iect to the following provision:
PSE8G 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.
...... -.. ~.
... =.
_ = -
-_. _. -. ~.. _
. ~ _.w
-a
. (8)
Solid Waste Process Control Program (Section 11.4.2, SER; Section 11.4, 55ER No. 4)
PSE&G shall obtain NRC approval of the Class B and C solid waste
~)robess control program prior to processing Class B and C solid wastes.
(9)
Emeroency Planning (Section 13.3, SSER No. 51 In the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication that a maior substantive problem exists in achieving or maintaining an adequate state of emergency preparedness, the provisions of 10 CFRSection50.54(s)(2)willapoly.
(10)
Initial Startup Test Program (Section 14, SSER No. 5)
Any changes to the Initial Startup Test Program described in Section 14 of the FSAR made in accordance with the shall be reported in accordance with 50.59(provisions of 10 CFR 50.59 b) within one month of such change.
(11)
Partial Feedwater Heating (Section 15.1, SER; Section 15.1, 55ER No. 5; Section 15.1, 55ER No. 6)
The facility shall not be operated with reduced feedwater temperature for the purpose of extending the normal fuel cycle.
After the first operating cycle, the facility shall not be operated with a feedwater heating capacity that would result in a rated power feedwater temperature less than 400'F unless analyses sup-porting such operation are submitted by the licensee and approved by the staff.
(12)
Detailed Control Room Design Review (Section 18.1, SSER No.51 a.
PSEAG shall submit for staff review Detailed Control Room Design Review Summary 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, PSEAG shall provide temporary zone markings on safety-related instruments in the control room.
9
~.-..---=~-.~~__~mm==..-
- ~. ~.,... _ ~ _ _..
2.
(13) Safety Parameter Disolay System (Section 18.2, SSER No. 5)
Prior to restart following the first refueling outage, PSE&G shall,
- per its commitment made in a letter dated March 7, 1986, add the following parameters to the SPDS and have them operational
a.
Primary containment radiation b.
Primary containment isolation status c.
Combustible gas concentration-in primary containment d.
Source range neutron flux D.
The facility requires exemptions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70. An exemption from the criticality alarm require-ments of 10 CFR 70.24 was granted in Special Nuclear Material License No.
1953, dated August 21, 1985. This exemption is described in Section 9.1 of Supplement No. 5 to the SEP.. This previously granted exemption is continued in this operating license. An exemption from certain require-ments of Appendix A to 10 CFR Part 50, is described in Supplement No. 5 to the SER. This exemption is 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 R 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 requirement of Paragraph III.D.2(b)(fi) of Appendix J, exempting overall 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 Appdndix 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 thermal 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 reoarding 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.
v----.m--
,m,-
--w.--
ne,-
,w,,,-.-, - - -
,,w,,,,
.,----,_-,----,-,,yy y
4q,_
,,,_,-,e~
,.3.._
m.m.m.m.m e m 3.m.m.=m.2 u - =,=.rg; mg.aca; -
m
. 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 Comission and all ar,end-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 Environ-mental Protection Plan, PSEAG 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).
G.
The licensees shall have and maintain financial protection of such type and in such amounts as the Comission shall require in accordance 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 REGillATORY COMMISSION a
Harold R. Denton, Director Office of Nuclear Reactor Regulation
[
Enclosures:
1.
Appendix A - Technical Specifications (NUREG-1202) 2.
Appendix B - Environmental Protection Plan Date of Issuance:
July 25,1986 i
l
!