ML20199L139
| ML20199L139 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 04/08/1986 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8604100299 | |
| Download: ML20199L139 (10) | |
Text
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e Pubhc Service Electric and Gas Company Crrbin A. McNeill, Jr.
Public Senace Electnc and Gas Company P.O. Box 236, Hancocks Bndge NJ 08038 609 339-4800 Vice Pres: dent.
Nucw April 8,1986 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Attention:
Ms. Elinor Adensam, Director Project Directorate 3 Division of BWR Licensing
Dear Ms. Adensam:
DRAFT LOW POWER LICENSE HOPE CREEK GENERATING STATION DOCKET NO. 50-354 Your letter of April 4, 1986 forwarded a draft copy of the Hope Creek Generating Station (HCGS) Low Power License for review to ensure that it accurately reflects commitments made by Public Service Electric and Gas Company (PSE&G).
As a result of our review of the draft low power license, we offer the following comments:
1.
Section 2.C (5) Environmental Qualification, Item b should be amended to read:
" Prior to achieving initial criticality, the 53 Tobar Model 32, Series 2 transmitters included in the Harsh Environmental Qualification Program shall be replaced with qualified Rosemount Model 1153B transmitters."
Underlined portion revised or added to be consistent with information contained in letter from C.A. McNeill, PSE&G to E.
Adensam, NRC dated March 26, 1986.
2.
Section 2.C (13) Detailed Control Room Design Review, Item b should be amended to read:
" Prior to restart following the first refueling outage, PSE&G shall provide temporary zone markings on safety-related instruments in the control room."
Underlined portion revised as it is PSE&G's preference, from a human factors viewpoint, that sufficient operating experience be gained before zone markings are added.
8604100299 060400 PDR ADOCK 05000354
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t Director of Nuclear 2
4/8/86 Reactor Regulation i
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Section 2.D; Page 7 - Appendix J exemption, Item (a)
I should be amended to read:
"(a) an exemption from the requirement of Paragraph III.D.2(b)(ii) of Appendix J, exempting overall containment air lock leakage testing t
unless maintenance has been performed on the air lock that could affect the air lock sealing capability (Section 6.2.6 of SSER 5)".
Underlined portion added to be i
consistent with HCGS Exemption Request No. 5 contained in letter from C.A. McNeill, PSE&G to E. Adensam, NRC l
dated December 12, 1985, HCGS Final Draft Technical Specification Section 4.6.1.3.b.2, and SSER 5 Section 6.2.6.
4.
Section 2.D; Page 7 - Appendix J exemption, Item (e) l should be amended to read:
"(c) an exemption from i
Paragraph III.C.2(a) of Appendix J, exempting Type C testing of thermal relief valves (Section 6.2.6 of I
SSER 5)."
Underlined portion added to reference appro-priate section of SSER 5.
l 1
Also, attached is a marked-up copy of the draft HCGS Low I
Power License which reflects the above items and additional 1
minor editorial comments.
1 PSE&G will be ready for issuance of the HCGS Low Power
- j License on April 10, 1986.
Please contact us if any additional information is required in the interim.
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Sincerely, I
t Attachment C
D.H. Wagner j
USNRC Licensing Project Manager 4
l R.W.
Borchardt i
USNRC Senior Resident Inspector I
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UNITED STATES p
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NUCLEAR REGULATORY COMMISSION 4
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6 PUBLIC SERVICE ELECTRIC & GAS COMPANY AND ATLANTIC CITY ELECTRIC COMPANY 10UCkE710. 50-3!i4
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HOPE CREEK GENERATING STATI0h FACILITY OPERATING LICEN5i License No. NPF-50 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
f 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 recuired notifications to c:ner 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 regulations of the Comission; C.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission (ex. cept as exempted from compliance in Section 2.D. below);
D.
There is reasonable assurance: (1) that the activities authorized by this eperating license een be eenducted without endanged ng 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 (except as exenpted from compliance in Section 2.D.
below);
E.
Public Service Electric & Gas Ccmpany* 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 Agreements," of the Comission's regulations; G.
The issuance of this license will not be inimical to the comon 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
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Electric Company and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
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2 H.
After weighing the environmental, economic, technical, and other benefits of the facility ag:in:t environmental and ether ccsts and considering available alternatives, the issuance of Facility Operating License No. NPF-50, subject 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 Cor mission's regulations in 10 CFR Parts 30, 40 and 70.
I 2.
Based on the foregoing findings regarding this facility, Facility Operating License No. NPF-50 is hereby issued to the Pubite Service Electric & Gas Company and Atlantic City Electric Company (the licensees) to read as follows:
A.
This license applies to the Hope Creek Generating Station, a boiling water nuclear reactor, and associated equipment (the facility) owned by Public Service Electric & Gas Company and Atlantic City Electric Ccmpany. 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 approximately eight miles southwest of Salem, New Jersey and is described in the Public Service Electric & Gas Company's M inal Safety Analysis Report f as supplemented and arrended, and in the its Environmental Report as supplemented and amended.
>3 E.
Subject to the conditions and requirements incorporated heroin, the Comission hereby licenses:
(1) Public Service Electric & Gas Company (PSE&G), pursuant to Section 103 of the Act and 10 CFR Part $0 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 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 required for reactor operation, as described in the Final Safety Analysis Report, as supplerrented and amended;
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. (4) PSE&G pursuant to the Act and 10 CFp Parts 30. 40 and 70, to receive, possess, and use at any time any byproduct. source and special nuclear material as sealed neutron sources foe reactor startup, sealed sources for reactor instrumentation and radiation monitor-ing equipment calibration. and as fission detectors in amocnts 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 requireo any byproduct, source or special nuclear material withc1t restriction to chemical or physical form, for sample analysis or instrument calibration or associated I
with radioactive apparatus or co:nponents; 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 faciljty.
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 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Comission now or here-after in effect; and is subject to the additional conditions specified or incorporated belo c (1) Maxir:um Power Level PSE&G is authorized to operate the facility at reactor core power levels not in excess of 3293 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein and in Attachment I to this license.
The preoperational tests, startup tests, and other items identified in Attachment I to this license shall be completed as specified. Attachment 1 is hereby incorpor-ated.into this license.
Pending Ctunission approval, this license is restricted to power levels not to exceed five percent of rated power (164.65 megawatts thermal).
(2) Technical Specifications and Environmental Prctecti_on Pla_n The Technical Specifications contained in Appendix A and the Cn-virontrental 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.
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o (3) Turbine Systern Maintenance Procram (Section 3.5.1.7.3, SE4; 5ecUon 3.6.1.3.3~, 55bt ho, f)*
PSE&G shall submit e turbine system raintenance pNgram based on the manufacturer ; calculations of Hstile-genereted proba-bilities by na later than 3 years fecn the date of th15 11 cense.
(4) Inservice Testing of Pumes and Va_lves (Settio-3.9_._C, SSER_No. 41 P rsut'it tc 10 CFR 50.55a and for the reasons set fort'n in Section 3.9.6 of SSER No. 4, the relief identified in the PSUG submittal dated July 12, 1985, requesting relief from eartein l
puTp and valve testing requircr.ents of IQ CFR 50.55e(g) is granted, ;
for a pericd of no longcr than two years fecm the date of iscuance of this license or until e decafled review of the inwrvice testing program for pumps anJ valv:s. has been crerpleted, which-ever comt.i first.
(5),E_nvircnmenta'iOuali<icati6n(secticn3.11.5,SSEhh5) a.
Prict to startup following the first f efueling outage, the qualified life of the electrical eayipment une r porcnase orde* M-48 shtll be recalculated on the basis of the actual tarperatures menitored et the equipment loce.tions during the margh,eycleofoperation,withada4Uate.considerationof UI5 nelJe/;n4de j,gg 33, hm :. cov;w,-aq 1"* O O b.
Prfor to achievin( initial criticality Tober Model 32, P"F Serics 2 transmittersAshell be replaced with qudlified Rospmeunt Mcdel 1153 nsmitters.
(5) gserv_iceinspection(Section6.6,SER: Section1 G.2.4.3 and
- c. C, 55EP.Tio, y a.
PSE&G shall submit an inservice inspection progrc'n in accorthnce with 10 CFR 50.55a(g)(4) for staff review within six mentks of l
the issuance of this license, b,
Pe-sucnt to 10 CTR 59.55a(a)(3) cnd for the reasons set i
forth in Se 2. ions 5.2.4.3 and 6.6.3 of SSER Na. 5, the
[.gy_,__ relief identified in.the F5E8G submittal dated Fovember 18, 1985, as revised Sy~lsubmittal dated January 20, 1986, reques tin i
50.55a(g)g relief from certain requirements of 10 CFR for the preservfee inspection program, is granted.
W parNI.ifetic31 notation following the title of many license corditions denotes the sectioc of the Safety Evaluation Report and/or its supplements wherein the License condition is discussed.
i
..a (7) g Storaje_ and HendlingSection 9.1, SSER No._5) 4.
'No more than a total ci' three (3) fuel ussemblies shall be out of approved stipping containers or fuel assembly storage racks or the resctor at any one time.
b.
The above three (3) fuel assenblies as a grcup shall maintain a minimum edge-to-edgk spacing of twelve (12) inches from the
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shipping container nrray end the storage rack arrby.
c.
Fresh fuel assemblies, when stored in their shipping con-tainers, shall be stacked no more than three (3) containers high.
(C)
Firo Prottetion Isaction 9.'s.l.8, SSER No. 5)
PSE5G shall implement and maintain in effect all provisions of the eppr6 sed fire protection progebm as described in the Final Safety Analysis Repcrt for the facility through Amehdment No.14 and as described in submittals dated Austst 12 and 27, November 21 and 29, December 3 and 16. 1985, and January'3, 1986, and as approved ir.theSERdatedOctober1984(andSupplements1through5) subject to the follcwing provision {hbc -
The licensee may make changes to the approved fire protection program without prior approval of the Comission only if those changes wculd not adversely affect the ability to echieve and maintain safe shutdown in the event of a fire.
(9) Solid Waste Process Control Program (Sectior,11.4.2, STR:
Sect. inn 11.4, 55ER No. 4)
M&G shall obtain NRC approval of the Class B and C solid Waste process contral program prior to processing Class B and C solid estes..
(10) Emergency Planning (Section 13.3, 55ER_No. 51 Ir. the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Mana0ement Agency's final rule, 44 CFR Part 350, is an indication that a major substantive problem exists 13 achieving or maintaining an adequate state of emergency preparedness, the provisions of
)
10 CFR Section 50.54(s)(2) will apply.
i (11) Initial Startup Test Procram (Section 14 SSER No. 5)
Any changes to the initial Test Prcgram described in Section 14 of the F5AR made in accordance with the provisions of 10 CFR 50.59 i
shall be reported in accordince with 50.59(b) within one month of such change.
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ObCM 5 13:31 NO.009 007 (12) P_artial Feedwster _ Heating (Section 15.1, SER; Section 15.1, 55ER hn. 5)
PSE&G shall not operate the facility (other than for normal start-up or shutdown) with the feedwater inlet temperature less than 424.5'F.
(13) Cetailed Control Room Design Review (Section 18.1, SSER No.5) a.
PSELG shall submit for staff review Detailed Control Room consistent with, and with contents as specified in,-ee44*-[ its.
Ocsign Review Summary Reports II and III on a schedule rester fcIIcenj letter of January 9,1986.
se. kt refueliaS
_b.
Prior to[exceedig #%+-percent pse, P3E&G shall provide conc.
temporary zone markings on safety-related instruments in the control room.
(14) Safety Parameter Display System (Section 18.2, SSER No. 5)
Prior to restart following the first refueling outage, the licensee 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 m
b.
Primary containment isolation status c.
C00bustible gas concentration in primary containment d.
Source range neutron flux 3.
The facility requires exemptions from certain requirements of 10 CFR Part 50 anc' 10 CFR Part 70 An exemption from the criticality alarm requirements of 10 CFR 70.24 was granted in Special Nuclear Material License No. 1953, dated August 21, 1985.
This exemption is described in.Scction 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 Supplenent No. 5 to the SER. These include (a) a schedular exemption to the requirements of General Design Criterion 17, pennitting delaying completion of preoperational testing 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 preoperational 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 Systen until prior to fully tensioningthereactorpressurevesselheadclosurebolts(Appendix R of SSER 5); (d) a schedular exemption to the requirements of General DDAET
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_. tkat could affect ble g;,. l, c ic Sealia) cAPakilifj Design Criterion 64, pemitting 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. 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 !!!.D.2(b)(ii) of Appendix J. exempting overall containment air lock leakage testing unless maintenance has been performed on the air lockA(Section 6.2.6 of SSER 5); (b) an exemption from the recuire-ment of Paragraph III.C.2(b) of Appendix J exempting main steam isolationvalveleak-ratetestingat1.10Pa(Section5.2.6ofSSER5);
c' (c) an exemption from Paragraph III.D.3 of Appendix J, exempting Type C testing)on transverse incore probe system shear valves (Section 6.2.6 of SSER 5 ; (d) an exemption from Paragraph III.D.2(a) of Aependix 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 (Suh.n d.r.(,
from Paragraph III.C.2(a) of Appendix J, exempting Type C testing of of53ER5).
themal reTief valvesA These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the comon defense and security.
The special circum-stances 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 Comissio%
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 infonnatJon protected under 10 CFR 73.21(m), are entitled:
" Hope Creek Generating Station Security Plan," with revisions submitted through March 20, 1985 " 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 su,bmitted through July 23, 1985.
F.
Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, PSE&G 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 Systemwithwrittenfollowupwithinthirty)daysinaccordancewith 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 FOR THE NUCLEAR REGULATORY COMMISSION Harold R. Denton, Director Office of Nuclear Reactor Regulation
Enclosures:
- 1.
2.
Appendix A - Technical Specifications (NUREG-1186) 3.
Appendix B - Environmental Protection Plan Date of Issuance:
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