ML20134F344
| ML20134F344 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 08/08/1985 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20134F346 | List: |
| References | |
| NUDOCS 8508210067 | |
| Download: ML20134F344 (11) | |
Text
-___
&g,0
- 9 UNITED STATES
-[
%)
NUCLEAR REGULATORY COMMISSION O
- p WASHINGTON, D. C. 20555 4,
,o#
PHILADELPHIA ELECTRIC COMPANY DOCKET NO 50-352 LIMERICK GENERATING STATION, UNIT 1 FACILITY OPERATING LICENSE License No. NPF-39 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found 1
that:
~
..A.
The application for license filed by Philadelphia Electric Company (the licensee) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I, and all required notifica-tions to other agencies or bodies have been duly made-i B.
Construction of the Limerick Generating Station, Unit 1 (the facility) has been substantially completed in conformity with Construction i
Permit No. CPPR-106 and the application, as amended, the provisions of the Act and the regulations of the Commission; C.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission (except as exempted from compliance in Section 2.D. below);
D.
There is reasonable assurance: (i) 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 Commission's regulations set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.D.
below);
E.
The licensee is technically qualified to engage in the activities authorized by this license in accordance with the Commission's regula-tions set forth in 10 CFR Chapter I; F.
The licensee has satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements", 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; 8508210067 850 BOB:
PDR ADOCK 05000352 P
. H.
After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering availeble citernatives, the issuance of this Facility Operating License ho. hPF-39, subject to the conditions for protection of the environment set forth in the Environmental Protection Plan attached as Appenoix 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 Comission's regulations in 10 CFR Parts 30, 40 and 70.
~
2.
- Based on the foregoing findings, the Partial Initial Decisions issued by the Atomic Safety and Licensing Boaro dated March 6, 1983, August 29, 1984, May 2, 19E5 and July 22, 1985, and the Decision of the Appeal Board dated September 26, 1984, regarding this facility, End approval by the Nuclear Regulatory Concission in its Memorandum ano Order dated August C,1985, the license for Fuel Loading and Low Power Testing, License No. NPF-27, issued on Octcber 26, 1984, is superseded by Facility Operating License hPF-39 hertby issbec to the Philadelphia Electric Company (the licensee), to read as follows:
A.
This license applies to the Limerick Generating Station, Unit 1, a boiling water nuclear reactor and associated equipment, owned by Philadelphia Electric Company. The facility is located on the licensee's site in Montgonery and Chester Counties, Pennsylvania on the banks of the Schuylkill River approximately 1.7 miles southeast of the city limits of Pottstown, Pennsylvania and 21 miles northwest of the city limits of Philadelphia, Pennsylvania, and is described in the licensee's Final Safety Analysis Report, as supplemented and amended, and in the licensee's
.Invironmental Report-0perating License Stage, as supplemented and
' amended.
~
B.
Subject to the conditions and requirements incorporated herein, the Comission hereby licenses Philadelphia Electric Cenpany:
(1) Pursuant to Section 103 of the Act and 10 CFR Part 50, to pos-sess, use, and operate the facility at the designated location in hontgomery and Chester Counties, Pennsylvania, in accordance with the procedures and limitations set forth in this license; (2) Pursuant to the Act and 10 CFR Part 70, to receive, possess and to use at any time special nuclear materihl as reactor fuel, in accordance with the limitations for storage and amcunts required for reactor operation, as described in the Final Safety Analysis Repcrt, as supplemented and amended; y
(3)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess ari use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitor-ing equipment calibration, and as fission detectors in anounts as required; (4) 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 (5) Pursuant to the Act ano 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 Consnission's regulations set forth in 10 CFR Chapter 1 (except as exempted fron cor.pliance in Section 2.D. below) and is subject to all applicable provisions of the Act and tc the rules, regulations, and orders of the Comission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level The licensee is authorized to operate the facility at reacter core power levels not in excess of 3293 megawatts therni (100% rated power) in accordance with the conditions specified herein and in Attachment 1 to this license. The itens identified in Attachment 1 to this license shall be completed as specified. is hereby incorporated into this license.
(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.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Fire Protection (Section 9.5, SSER-2)*
a.
The licensee shall maintain in effect all provisions cf the approved fire protecticn program as described 1.n the Final Safety Analysis keport for the facility through Rcvision 34 and as approved in the SEh through Supplement 2, and in the Fire Protection Evaluation Report thrcugh kevision 6, subject to provisions b and c below.
b.
The licensee shall make no change to features of the apprcved fire protection program which wculd decrease the level of fire protection in the plant without prior approval of the Connission. To nake such a change the licensee must submit an application for license amendment pursuant to 10 CFR 50.90, c.
The licensee may nake changes to features of the approved fire protection program which do not decrease the level of fire protection without prior Corrission approval after such fcatures have been installed as approved, provided such changes de not otherwise involve a change in a license con-oition or technical specification or result in an unreviewed safety question (see'10 CFR 50.59). However, the lica,sec shall naintain, in an aucitable form, a current record of all such changes incluoing an evaluation of the effects of the change on the fire protection progran and shall make such records available to NRC inspectors upon request. All changes to the approved progrcn nade without prior Comission approval shall bc reported to the Director of the Office of Nuclear Regulation, together with supporting analyses, annually.
d.
The licensee shall provide a stairway for fire brigadt access frota the turbine building to the Unit I cabic spreading roon via the Unit 2 cable spreading roon and the static inverter room prior to startup following the first refueling cutage.
- The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements whercin the license condition is discusseo.
(4) Qualification of Personnel (Section 13.1.2.2, SER and SSER-3 and SSER-4)
The licensee shall have on each shift operators that meet the requirements described in Attachneht 2.
(5) Emergency Response Capabilities (Generic Letter 82-33, Supplenent 1 to NUREG-0737) Safety Parameter Display System (Section 18.2, SER and SSER-3 and SSER-5)
The licensee shall have the Safety Parameter Display System operable within 30 days after the completion of the 100-Hour Warranty Run.
(6) Post - Fuel Lcading Initial Test Program (Section 14, SER and
~
Any changes to the Initial Test Progran described in Section 14 of the FSAR raade in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within cne month of such change.
(7)
Inservice Ins 3ection Program (Section 5.2.4.3 and 6.6.3, SE1 and SSER-3)
The licensee shall submit the inservice inspection program by October 26, 1965 for tiRC staff review and approval.
(8) Salem ATUS Event, Generic Letter 83-28 (Section 15.6, SSER-2)
The licensee shall implement its connitnents applicable to Generic Letter 83-28 on a schecule which is consistent with that given in its November 10, 1983, May 8, 1984 and June 7, 1984
' letters.
(9) Turbine System Maintenance Progran (Section 3.5.1.3, SER)
The licensee shall submit a turbine system maintenance program by October 26, 1987.
Prior to review and approval of that program by the NRC staff, the licensee shall volumetrically inspect all low pressure turbine rotors at the second refueling outage and every other (alternate) refueling outage thereafter.
1 l
(10) Reactor Enclosure Cooling Water and Chilled Water Isolstion Valves (Section 6.2.4.2, SER and SSEk-3)
The licensee shall, prior to startup following the first refuel-ing outage, provide automatic and diverse isolation signals to the reactor erclosure cooling water inboard anc outbo6rd isolation valves in the supply and return lines to the recirculation pumps and the drywell chilled water outboard isolation valves in the supply and return lines.
(11) Hydrogen Recombiner Isolation (Section 6.2.4.2, SER and SSER-1 and SSER-3)
The licensee shall, prior to startup following the first refuel-ing outage, install and test an additional automatic isolation valve in each of the hydrogen recombiner lines penetrating the primary containment.
(12) Remote Shutdcyn System (Sections 7.. 4.4, 7.4.2.3, SEk anc Section 7.4.2.3, SSER-3 and SSER-5)
The licensee shall, prior to startup following the first refueling outage, have ccmpleted modifications to the existing remote shutdown system to provide a redundant safety-related method of achieving safe shutdown conditions withcut lifting leads or adding jumpers.
The modifications to be completed shall be those described in the licensee's letters dated April 18 and 22, 1985 which allow for the operation of the B RHR pump, the B RHR SU pump and the B ESW pump
.from the respective puup breaker compartnients by the installation of transfer switches. The licensee shall perform necessary tests prior tc startup following the'first refueling outage to demonstrate the operability of the modifieo system.
(13) Operation with Partial Feedwater Heating at End-of-Cycle (Section 15.0, SER)
The facility shall not be operated with partial feedwater heating for the purpose of extending the nonnal fuel cyclc.
(14)RefuelingFloorVolumeConnectiontoStandbyGasTreatment Systen (Section 6.2.3, SSER-2 and SSER-3)
Prior to any movement of irradiated fuel within the ' refueling floor volume the licensee shall ccmplete and test all moaifi-cations required to connect the refueling floor vclune to standby gas treatment system. During the interin period, the licensee shall not remove the reactor pressure vessel heaa prior to the NRC staff review and approval.
(15) Emergency Planning Procedures Subject to 44 CFR Part 350 In the event the NRC finds that the lack of progress in comple-tion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication that a major 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.
D.
The facility requires exemptions from certain requirements of 10 CFR Part 50. These include (a) exemption from General Design Criteria (GDC) 61 of Apperdix A, operation of that portion of the standby gas treatment system (SGTS) that serves the refueling area until the first refueling (Section 6.2.3 of SSER-2 and SSER-3), (b) exemption from GDC-56 of Appendix A, the requirement for additional automatic containment isolation valves for the hydrogen recombiner lines and the requirement for automatic isolation of existing isolation valves in the Drywell Chilled Water (DCW) and the Reactor Enclosure Cooling Water (RECW) systems until prior to startup following the first refueling outage (Section 6.2.4.2 of the SER, SSER-1 and SSER-3), (c) exemption from GDC-19 of Appendix A, as related to the requirement for redundant remote shutdown capability (Section 7.4.2.3 of SSER-S and SSER-5), (d) exenption from the requirement of paragraph III.D.2.(b)(ii) of Appendix J, the testing of containment air locks at times when the containment integrity is not required (Section 6.2.6.1 of the SER and SSER-3),
(e) exemption from the requirements of paragraphs 11.H 4. and III.C.2 of Appendix J, the leak rate testing of the Main Steam Isolation Valves (MSIVs) at the peak calculated containment pressure. Pa, and exemption from the requirements of paragraph III.C.3 of Appendix J that the measured MSIV leak rates be included in the sumation for the local leak rate test (Section 6.2.6 of SSER-3), (f) exemption from the requirement of paragraphs ll.H.1 and III.C.2 of Appendix J, the local leak rate testing of the Traversing Incore Probe Shear Valves (Section 6.2.6 of the SER and SSER-3),(g) a one-time exemption from the requirement of Appendix J to perform local leak
=
rate testing on seven Residual Heat Removal Relief Valves (Section 6.2.6 of SSER-3) (h) exemption from requireuent of 10 CFR Part 50.44, the incrting of containment six months af ter initial criticality (Section 6.2.5 of SSER-5) ano (i) exemption from the requirements of sq 10 CFR Part 50, Appendix E, Section IV.F.1 for the conduct of a full participation emergency preparedness exercise within one year befcre the issuance of a full power operating license (Section 13.3 of SSER-6). These exemptions are authcrized by law and will not endanSer life or property or the cormon defense and security and are otherv:ise in the public interest. Therefore these exeniptions are hereby granted pursuant to 10 CFR 50.12 and 50.47(c). With the granting of these exemptions the facility will operate, to the extent authorized herein, au in conformity with the application, as amended, the provisions of the is Act, and the rules and regulations of the Connission, y
E.
The licensee shall fully implement and maintain in effect all provisions of the Commission-upprcved physical security, guard training ano qualification, and safeguards contingency plans, including all ameno-ments and revisions rade pursuant to the authority of 10 CFR 50.90 anc 10 CFR 50.54(p), which are part of the license. These plans, which ccntain Safegaurds Infornation prctected under 10 CFR 73.21, are entitieo:
" Limerick Generating Station Physical Security Plan," " Limerick Generating
]
Station Plant Security Personnel Training and Qualification Plan," and "Linierick Generating Station Safeguards Contingency Plan."
F.
Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, the licensee 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 vic the Energency Notification Systen with written followup within thirty days in accordance with the procedures described in 10 CFR 50.73(b), (c), and (e).
G.
The licensee shall have and maintain financial protection of such type and in such amounts as the Conmission shall require in accord-ance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability clains.
g i
l s
i
H.
This license is effective as of the date of issuance and shall expire at midnight on October 26, 2024 FOR THE NUCLEAR REGULATORY C0l4115510N i ector Office of Nuclear Reactor Regulation Attachments / Appendices:
- 1. - Attachments 1-2 2.
Appendix A - Technical Specifications (NUREG-1149) 3.
Appendix B - Environmental Protection Plan Date of Issuance: AUG 0 8 W
ATTACHMEtiT 1 To-NPF 39 The attachment identifies itens which n.ust be completed to the satisfaction of the staff in accordance with the operational nioces or conditions identified below.
1.
OUTSTAt!DIt;C ITEh TO BE ACCOMPLISHED PRIOR TO INITIALLY INERTING THE CONTAIhMEhl AS REQUIRED BY TECHNICAL SPECIFICATI0h5 3/4.6.6.3 AhD 3/4.10.5 Complete the nodifications to the liquid nitrogen vaporization f
facility ano the containment inerting system described in the licensee's letter dated Septer.ber 26, 1984 or alternate modifications determined i
acceptable followins an evaluation per 10 CFR 50.59 (IE Bulletin 84-01)
)
In the event alternate modifications are used, describe these
~~ mcdifications and their supportino bases in a report to NRC Region I l
within thirty days of their inplementation.
2.
OUTSTAt:CIhG ITE!!S TO BE CORRECTED BY THE FIRST REFUELING OUTAGE a.
Seal the conduits to instruments in the pipe tunnel.
(Inspection Report 50-352/84-27 Item 04) b.
Complete the actions for Construction Deficiency Report (84-00-10
" Water accumulation in diesel fuel oil tanks.")
ATTACHMEf.T 2 To NPF-39 This attachment identifies the shift operating staff experience requirements.
At all times the plant is in an operating condition other than cold shutdown or refueling, the licensee shall have a licensed senior operator on each shift who has had at least six months of hot operating experience on a sake type plant, including at least six weeks at power levels greater than 20% of full power, and who has had startup and shutdown experience.
For those shifts where such an inoividual is not available on the plant staff, an advisor shall be provided who has had at least four years of power plant experience, including two years of nuclear plant experience, and who has had at least one year of experience on shift as a licensed senior operator at a similar type facility. Advisors, as a minimum, shall be trained on plant procedures, technical specifications and plant systems, and shall be examined on these tcpics at a level sufficient te assure familiarity with the plant. These advisors or suitably qualified replacements shall be retained until at least one of the senior operators on each shift has the required experience. The NRC shall be notified at least 30 days prior to the release of any special assigned advisors.
D