ML20080B989
| ML20080B989 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/29/1994 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Philadelphia Electric Co, Public Service Electric & Gas Co, Delmarva Power & Light Co, Atlantic City Electric Co |
| Shared Package | |
| ML20080B992 | List: |
| References | |
| DPR-44-A-199, DPR-56-A-201 NUDOCS 9412070109 | |
| Download: ML20080B989 (31) | |
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- i UNITED STATES NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20666 4001
,o PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY STLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-277 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.199 License No. DPR-44 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated April 15, 1994, 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 (i) 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; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health or safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of 1
the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, pages 1, 2, 3, 4, 4a, and 5 of the Facility Operating License No. DPR-44 are hereby amended by changing Philadelphia Electric Company to PECO Energy Company.
3.
Further, 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. DPR-44 is hereby amended to read as follows:
9412070109 941129 PDR ADOCK 05000277 P-PDR
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. (2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Arendment No.199, are hereby incorporated in the license.
PECO sht.11 operate the facility in accordance with the Technical Specificnions.
4.
This license amendment is effective as of its date of issuance.
FOR TH N LEAR REGULATORY COMMISSION bdder
+W John F. Stolz, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachments:
1.
Pages 1, 2, 3, 4, and 5 of License No. DPR-44 2.
Changes to the Technical Specifications Date of Issuance: November 29, 1994
- Pages 1, 2, 3, 4, and 5 are attached, for convenience, for the composite license to reflect this change.
ATTACHMENT TO LICENSE AMENDMENT N0. 199 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET N0. 50-277 Replace the following pages of the Facility Operating License (F0L), the Appendix A Technical Specifications, and Appendix B Environmental Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Insert FOL 1
1 2
2 3
3 4
4 4a 5
5 Appendix A 99 99 116 116 117 117 216e 216e 249 249 256 256 Appendix B 14 14 41-47
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g UNITED STATES NUCLEAR REGULATORY COMMISSION E
f WASHINGTON D.C. 206f50001 QVR/
4..,+
PECO ENERGY COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION. UNIT 2 FACILITY OPERATING LICENSE License No. DPR-44 Amendment No. 1 1.
The Atomic Energy Commission (the Commission) having found that:
A.
The application for license filed by PECO Energy Company, formerly Philadelphia Electric Company, Public Service Electric and Gas Company, Delmarva Power and Light Company, 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 Commission's rules and regulations set forth in 10 CFR Chapter I and all required notifications to other agencies-or bodies have been duly made; B.
Cons ruction of the Peach Bottom Atomic Power Station, Unit 2 (the facility) has been substantially completed in conformity with Construction ~ Permit No.
CPPR-37 and the application, as amended, the provisions of the Act and the rules and regulations of the Commission; C.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; D.
There is reasonable assurance: (1) that the activities authorized by this amended operating license can be conducted without endangering the health and safety of the public, and (2) that such activities will be conducted in compliance with the rules and regulations of the Commission; E.
PECO Energy Company is technically qualified and the licensees are financially qualified to engage in the activities authorized by this amended operating license in accordance with the rules and regulations of the Commission; F.
The licensees have 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 amended operating license will not be inimical to the common defense and security or to the health and safety of the public; Page 1 Amendment No.199 i
H.
After weighing the environmental, economic, technical, and other benefits of the facility against environmental costs and considering available alternatives, the issuance of Amendment No. I to Facility Operating License No. DPR-44 is in accordance with 10 CFR Part 50, Appendix D, of the Commission's regulations and all applicable requirements of said Appendix D have been satisfied; and I.
The receipt, possession, and use of by-product and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30 and 70, including 10 CFR Section 30.33, and 70.23 and 70.31.
2.
Amendment No. I to Facility Operating License No. DPR-44 issued to the PECO Energy Company (PECO), formerly the Philadelphia Electric Company, Public Service Electric and Gas Company (PSE&G), Delmarva Power and Light Company (DP&LC), and Atlantic City Electric Company (ACEC), is hereby amended in its entirety to read as follows:
A.
This amended license applies to the Peach Bottom Atomic Power Station, Unit 2, a single cycle, forced circulation, boiling water nuclear reactor and associated equipment (the facility), owned by the licensees and operated by PECO Energy Company. The facility is located in Peach Bottom, York County, Pennsylvania and is described in the " Final Safety Analysis Report" as supplemented and amended (Amendments 1 through 29) and the Environmental Report as supplemented and amended (Supplements 1 through 6).
B.
Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:
(1)
PECO Energy Company, pursuant to Section 104b of the Act and 10 CFR Part 50, " Licensing of Production and Utilization Facilities," to possess, use, and operate the facility and PSE&G, DP&LC, and ACEC to possess the facility at the designated location in Peach Bottom, York County, Pennsylvania in accordance with the procedures and limitations set forth in this' license; (2)
PECO Energy Company, 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, as of December 15, 1975; (3)
PECO Energy Company, 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 startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
PECO Energy Company, 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 when associated with radioactive apparatus or components-i Page 2 Amendment No. Z8, 199
l (5)
PECO Energy company, pursuant to the Act and 10 CFR Parts 30 and 70, to l possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility.
C.
This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:
Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
(1)
Maximum Power level PECO Energy Company is authorized to operate the Peach Bottom Atomic l
Power Station, Unit 2, at steady state reactor core power levels not to exceed 3458 megawatts thermal.
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised,
through Amendment No.
are hereby incorporated in the license.
PECO Energy Company shall operate'the facility in accordance with the Technical Specifications.
(3)
The licensees may perform modifications to the Low Pressure Coolant Injection System as described in the licensees' application for license amendment dated July 9, 1975. The licensees shall not operate the facility prior to receipt of the Commission's authorization.
(4)
Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical. security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:
" Peach Bottom Atomic Power Station, Units 2 and 3, Physical Security Plan," with revisions submitted through December 16, 1987;
" Peach Bottom Atomic Power Station, Units 2 and 3 Plant Security Personnel Training and Qualification Plan," with revisions submitted through July 9, 1986; and " Peach Bottom Atomic Power Station, Units 2 and 3 Safeguards Contingency Plan," with revisions submitted through March 10, 1981.
Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
(5)
The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility, and as approved in the NRC SER dated May 23, 1979 and Supplements dated August 14, September 15, Page 3 Amendment No. I#, IS, 53, 7S.
135, 19#, 198,199
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October 10 and November 24, 1980, and in the NRC SERs dated September 16, 1993 and August 24, 1994, subject to the following provision:
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.
3.
This amended license is subject to the following conditions for the protection of the environment:
A.
Upon completion of the licensees' " smoke tests," the licensees shall release all procedures, data, and analysis bearing on the calculation of X/Q to the Regulatory Staff as soon as possible but no later than initial fuel loading for Peach Bottom Unit 3.
Using the " smoke test" results to re-calculate X/Q and using the other assumptions previously used by the Regulatory Staff (or realistic refinements thereof), the Regulatory Staff shall re-calculate the potential radiciodine thyroid dose to a child via the milk pathway at the points of maximum concentration at or beyond the site boundary where dairy cows are present or could be pastured.
If this calculated dose based on the combined operation of Peach Bottom Units 2 and 3 exceeds 15 mrem / year, then the licensees shall install for operation no later than the next refueling cycle for each unit the necessary equipment to reduce the projected dose to such iavels.
B.
If the actual milk sample measurements taken at the nearby farms in accordance with the Technical Specifications, predict a dose to a child's thyroid, based on actual combined operation of Unit 2 and 3, that exceeds 15 mrem / year, licensees shall install for operation no later than the next refueling cycle for each unit the necessary equipment to reduce the projected dose to such levels.
C.
To the extent matters related to thermal discharges are treated therein, l
operation of Peach Bottom Atomic Power Station Unit No. 2 will be governed by NPDES Permit No. PA 0009733, as now in effect and as hereafter amended.
Questions pertaining to conformance thereto shall be referred to and shall be determined by the NPDES Permit issuing or enforcement authority, as appropriate.
D.
In the event of any modification of the NPDES Permit related to thermal discharges or the establishment (or amendment) of alternative effluent limitations established pursuant to Section 316 of the Federal Water Pollution Control Act, the licensees shall inform the NRC and analyze any associated changes in or to the Station, its components, its operation or in the discharge of effluents therefrom.
If such change would entail any modification to this license, or any Technical Specifications which are part of this license, or present an unreviewed safety question or involve an environmental impact different than analyzed in the Final Environmental Statement, the licensees shall file with the NRC, as applicable, an appropriate analysis of any such change on facility safety, and/or an analysis of any such change on the environmental impacts and on the overall cost-benefit balance for facility operation set forth in the Final Environmental Statement and a request for an amendment to the operating license, if required Page 4 Amendment No. 52, 53, 19#, 199
by the Commission's regulations. As used in this Condition 3.(d), Final Environmental Statement means the NRC Staff Final Environmental Statement related to Operation of Peach Bottom Atomic Power Stetion Units Nos. 2 and 3 dated April 1973, as modified by (1) the Initial Decision of the Atomic Safety and Licensing Board dated September 14,1973,(2) the Supplemental Initial Decision of the Atomic Safety and Licensing Board dated June 14, 1974, (3) the Decision of the Atomic Safety and Licensing Appeal Board dated July 5,1974, (4) the Memorandum and Order of the Commission dated August 8, 1974, (5) any further modification resulting from further review by the Appeal Board and by the Commission, if any, and (6) any Environmental Impact Appraisal which has been or may be issued by the NRC since the FES was published in April 1973.
4.
This license is effective as of the date of issuance and shall expire at midnight on August 8, 2013.
FOR THE ATOMIC ENERGY COMMISSION Original Signed by R. C. DeYoung, for A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing Attachments:
Appendices A and B -
Technical Specifications Date of Issuance: October 25, 1973 Page 5 Amendment No. 72, Ig6,199
Unit 2 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3 REACTIVITY CONTROL 4.3 REACTIVITY CONTROL Ano11cabilitn Aeolicability:
Applies to the operational Applies to the surveillance statm of the control rod requirements of the control Ustem.
rod system.
Ob.iective:
Ob.iective:
To assure the ability of the To verify the ability of the control rod system to control rod system to control reactivity.
control reactivity.
$oecification:
Specification:
A. Reactivity Limitations A. Reactivity Limitations
- 1. Reactivity marain -
- 1. Reactivity marain -
core loadina core loadina A sufficient number of control Sufficient control rods shall rods shall be operable so be withdrawn following a that the core could bb made refueling outage when core subcritical in the most alterations were performed to reactive condition during the demonstrate with a margin of operating cycle with the 0.38h k/k that the core can strongest control rod fully be made suberitical at any withdrawn and all other time in the subsequent fuel operable control rods fully cycle with the analytically inserted.
determined strongest operable control rod fully withdrawn and all other operable rods fully inserted.
- 2. Reactivity marain -
- 2. Reactivity marain -
inocerable control rods inoperable control rods a.
Control rods which cannot a.
Each partially or fully be moved with control rod withdrawn operable control drive pressure shall be rod shall be exercised one considered inoperable.
notch at least once each week when operating above If a partially or fully the RWM low power setpoint.
withdrawn control rod drive Each partially or fully cannot be moved with drive withdrawn operable control or scram pressure the rod shall be exercised at reactor shall be brought I
least one notch within 24 to a shutdown condition hours when operating above within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> unless the RWM low power setpoint if there are three
~99~
Amendment No.17, D,17I,199
Unit 2 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.4 STAND 8Y LIOUID CONTROL SYSTEM 4.4 STANDBY LIOUID CONTROL SYSTEM (Cont'd)
(Cont'd) 2.
Manually initiate one of the Standby Liquid Control System Pumps and pump demineralized water into the reactor veifsel from the test tank.
This test checks explosion of the charge associated with the tested loop, proper operation of the explosive valves, and pump operability. The replacement charge for the explosive valve shall be from the same manufactured batch as the one fired or from another batch which has been certified by having one of the batch successfully fired.
3.
Both systems, including both explosive valves, shall be tested in the course of two operating cycles.
B.
Normal System i ouirements B.
Normal System Reauirements At all times when the Standby Liquid Control System is required to be operable, the following conditions shall be met:
1.
At least 162.7 lbm Boron-10 1.
Baron-10 Quantity: At least once must be stored in the Standby per month calculate and record Liquid Control Solution Tank the quantity of Boron-10 stored i
and be available for injection.
in the Standby Liquid Control Solution Tank.
2.
The sodium pentaborate 2.
Concentration: At least once solution concentration must per month check and record.
be equal to or less than Also, check concentration 9.82% weight.
anytime water or boron is added to the solution.
-116-Amendment No. #7,122,199
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Unit 2 l
I PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.4 ETANDBY LIOUID CONTROL SYSTEM 4.4 STANDBY LIOUID CONTROL SYSTEM l
(Cont'd.)
(Cont'd.)
l 3.
The Standby Liquid Control System i
conditions must satisfy the following equation:
13% wt.
86 gpm 19.8% atom b 1
- where, C-Sodium Pentaborate Solution Concentration (% weight) l l
Q-Pump Flow Rate (gpm) 3.
Pump Flow Rate: At least j
against a system head of once per 92 days each pump l
l 1255 psig.
loop shall be functionally tested by pumping boron solution to the test tank.
At least once per quarter i
check and record pump flow rate agaim:t a system head of 1255 p ig.
l E-Boron-10 Enrichment (% atom 4.
Enrichment:
Following each.
Boron-10) addition of boron to the l
solution tank, calculate l
enrichment within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Verify results by analysis within 30 days.
5.
Solution Volume: At least once per day check and record.
-117-Amendment No. 2, 122, 198, 199
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Unit 2 PBAPS 6.5.2 Nuclear Review Board Function-6.5.2.1 The Nuclear Review Board (NRB) shall function to provide independent review and audit of designated activities in the area of:
- a. nuclear power plant operations
- b. nuclear engineering
- c. chemistry and radiochemistry
- d. metallurgy
- e. instrumentation and control
- f. radiological safety
- g. mechanical and electrical engineering
- h. quality assurance practices The members of the NRB will be competent in the area of quality assurance practice and cognizant of the Quality Assurance requirements of 10 CFR 50, Appendix B.
Additionally, they will be cognizant of the corporate Quality Assurance Program and will have the corporate Quality Assurance organization available to them.
Oraanization
)
6.5.2.2 The Chairman, members and alternate members of the NRB i
shall be appointed in writing by the Executive Vice President - Nuclear, and shall have an academic degree in an engineering or physical science field and in addition, shall have a minimum of five years technical experience, of which a minimum of three years shall be in one or more areas given in 6.5.2.1.
The NRB shall be composed of at least five members who are PECO Energy Company (PECO) employees and at least two outside members who are not PEC0 employees.
-249-Amendment No. 10, 37, #7, 63,1996),
II4, 132, 158,
Unit 2 PBAPS 6.9.1 Routine Reports (cont'd) c.
Annual Safetv/ Relief Valve Report Describe all challenges to the primary coolant system safety and relief valves. Challenges are defined as the automatic opening of the primary coolant safety or relief valves in response to high reactor pressure.
d.
Monthly Operatino Report Routine reports of operating statistics and shutdown experience and a narrative summary of the operating experience shall be submitted on a monthly basis.
Each report shall be submitted no later than the 15th of the month following the calendar month covered by the report, e.
Core Operatino Limits Report (1)
Core operating limits shall be established and shall be documented in the CORE OPERATING LIMITS REPORT prior to each Operating Cycle, or prior to any remaining portion of an Operating Cycle, for the following:
a.
The APLHGR for Specification 3.5.I, b.
The MCPR for Specification 3.5.K, c.
The core flow and power adjustment factors for Specification 3.5.K and 3.5.I, d.
The LHGR for Specification 3.5.J, e.
The upscale power biased Rod Block Monitor setpoints and corresponding power levels.
(2) The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents as amended and approved:
a.
HEDE-240ll-P-A, " General Electric Standard Application for Reactor Fuel" (latest approved version) b.
" Maximum ExteM N Load Line Limit and ARTS Improvement Pru am Analyses for Peach Bottom Atomic Power Station Units 2 and 3,"
NEDC-32162P, Revision 1, February, 1993 c.
PECO Energy Company Methodologies as described l
in:
(1)
PEco-FMS-0001-A, " Steady-State Thermal Hydraulic Analysis of Peach Bottom Units 2 and 3 using the FIBWR Computer Code" AmendmentNo.g,110,TH,160,792,
-256-
1 Unit 2 PBAPS 6.0 Environmental Surveillance and Special-Study Proarams Studies described in this section will be terminated upon agreement by PECO Energy Company and the Nuclear Regulatory Commission
~
that the intended purpose of the study has been satisfied.
6.1 (Deleted) 6.2 (Deleted) 6.3 (Deleted) i
)
I I
)
1 Note:
Pages 15-47 l
have been deleted.
The next page is 48.
l Amendment No. 67, 92, 199
' gaag 4
UNITED STATES y
NUCLEAR REGULATORY COMMISSION E
f WASHINGTON, D.C. 205 5 0001
\\...../
PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION. UNIT N0. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 201 License No. DPR-56 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated April 15, 1994, 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 (i) 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; i
D.
The issuance of this amendment will not be inimical to the common i
defense and security or to the health or safety of the public; and j
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, pages 1, 2, 3, 4, 4a, and 5 of the Facility Operating License No. DPR-56 are hereby amended by changing Philadelphia Electric Company to PECO Energy Company.
3.
Further, 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. OPR-56 is hereby amended to read as follows:
. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 291, are hereby incorporated in the license.
PEC0 shall operate the facility in accordance with the Technical Specifications.
4.
This license amendment is effective as of its date of issuance.
FOR TH UCLEAR REGULATORY COMMISSION
(
f'b. YL Fo' John F. Stolz, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachments:
1.
Pages 1, 2, 3, 4, and 5 of License No. DPR-56 2.
Changes to the Technical Specifications Date of Issuance: November 29, 1994
- Pages 1, 2, 3, 4, and 5 are attached, for convenience, for the composite license to reflect this change.
ATTACHMENT TO LICENSE AMENDMENT NO. 201 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following pages of the Facility Operating License (FOL), the Appendix A Technical Specifications, and Appendix B Environmental Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Insert FOL 1
1 2
2 3
3 4
4 4a 5
5 Appendix A 99 99 101 101 116 116 117 117 216e 216e 249 249 256 256 Appendix B 14 14 41-47
- " "C%
y 4
UNITED STATES l
j NUCLEAR REGULATORY COMMISSION l
t WASHINGTON, D.C. 20666-0001
%...../
i PECO ENERGY COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION. UNIT 3 FACILITY OPERATING LICENSE License No. DPR-56 1.
The Atomic Energy Commission (the Commission) having found that:
A.
The application for license filed by PECO Energy Company, formerly Philadelphia Electric Company, Public Service Electric and Gas Company, Delmarva Power and Light Company, 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 Commission's rules and 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 Peach Bottom Atomic Power Station, Unit 3 (the facility) has been substantially completed in conformity with Construction Permit No.
CPPR-38 and the application, as amended, the provisions of the Act and the rules and regulations of the Commission; C.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the iules and regulations of the Commission; 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 (2) that such activities will be conducted in compliance with the rules and regulations of the Commission; E.
PECO Energy Company is technically qualified and the licansees are financially qualified to engage in the activities authorized by this amended operating license in accordance with the rules and regulations of the Commission; F.
The licensees have 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 operating license will not be inimical to the common defense and security or to the health and safety of the public;
\\
Page i Amendment No. 201
H.
After weighing the environmental, economic, technical, and other benefits of the facility against environmental costs and cons;dering available alternatives, the issuance of Facility Operating License No. DPR-56 is in accordance with 10 CFR Part 50, Appendix D, of the Commission's regulations and all applicable requirements of said Appendix D hate been satisfied; and I.
The receipt, possession, and use of by-product 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, including 10 CFR Section 30.33, 40.32, and 70.23 and 70.31.
2.
Facility Operating License No. DPR-56 is hereby issued to the PECO Energy Company (PECO), formerly the Philadelphia Electric Company, Public Service Electric and Gas Company (PSE&G), Delmarva Power and Light Company (DP&LC), and Atlantic City Electric Company (ACEC), is hereby amended in its entirety to read as follows:
A.
This license applies to the Peach Bottom Atomic Power Station, Unit 3, a direct cycle, forced circulation, boiling water nuclear reactor and associated equipment (the facility), owned by the licensees and operated by PECO Energy Company.
The facility is located in Peach Bottom, York County, Pennsylvania and is described in the " Final Safety Analysis Report" as supplemented and amended (Amendments 1 through 31) and the Environmental Report as supplemented and amended (Supplements 1 through 6).
B.
Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:
(1)
PECO Energy Company, pursuant to Section 104b of the Act and 10 CFR Part 50, " Licensing of Production and Utilization Facilities," to possess, use, and operate the facility and PSE&G, DP&LC, and ACEC to possess the facility at the designated location in Peach Bottom, York County, Pennsylvania in accordance with the procedures and limitations set forth in this license; (2)
PECO Energy Company, 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, as of December 15, 1975; (3)
PECO Energy Company, 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 startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
PECO Energy Company, 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 when associated with radioactive apparatus or components; Page 2 Amendment No.17, 201
(5)
PECO Energy Company, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility.
C.
This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
(1)
Maximum Power level PECO Energy Company is authorized to operate the Peach Bottom Atomic Power Station, Unit 3, at steady state reactor core power levels not in excess of 3293 megawatts thermal.
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
are hereby incorporated in the license. PECO Energy Company shall operate the facility in accordance with the Technical Specifications.
(3)
Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:
" Peach Bottom Atomic Power Station, Units 2 and 3, Physical Security Plan," with revisions submitted through December 16, 1987;
" Peach Bottom Atomic Power Station, Units 2 and 3 Plant Security Personnel Training and Qualification Plan," with revisions submitted through July 9, 1986; and " Peach Bottom Atomic Power Station, Units 2 and 3 Safeguards Contingency Plan," with revisions submitted through March 10, 1981.
Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
(4)
The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility, and as approved in the NRC SER dated May 23, 1979 and Supplements dated August 14, September 15, October 10 and November 24, 1980, and in the NRC SERs dated September 16, 1993 and August 24, 1994, subject to the following provision:
i Page 3 Amendment No. 17, 33, 738, 198, 201 l
l i
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.
(5)
Operation beyond the end-of-cycle (all rods out condition) thermal power is limited to seventy (70) percent minimum.
Increasing core power level via reduced feedwater heating, once operation in the coastdown mode has begun, is not permitted unless the licensee has performed an analysis of this operating condition that confinns that this condition is bounded by the analysis for the particular cycle of operation.
3.
This license is subject to the following conditions for the protection of the environment:
A.
If the actual milk sample measurements tak.en at the nearby farms in accordance with the Technical Specifications, predict a dose to a child's thyroid, based on actual combined operation of Unit 2 and 3, that exceeds 15 mrem / year, licensees shall install for operation no later than the next refueling cycle for each unit the necessary equipment to reduce the projected dose to such levels.
B.
To the extent matters related to thermal discharges are treated therein, operation of Peach Bottom Atomic Power Station Unit 2 will be governed by NPDES Permit No. PA 0009733, as now in effect and as hereafter amended.
Questions pertaining to conformance thereto shall be referred to and shall be determined by the NPDES Permit issuing or enforcement authority, as appropriate.
C.
In the event of any modification of the NPDES Permit related to thermal discharges or the establishment (or amendment) of alternative effluent limitations established pursuant to Section 316 of the Federal Water Pollution Control Act, the licensees shall inform the NRC and analyze any associated changes in or to the Station, its components, its operation or in the discharge of effluents therefrom.
If such change would entail any modification to this license, or any technical specifications which are part of this license, or present an unreviewed safety question or involve an environmental impact different than analyzed in the Final Environmental Statement, the licensees shall file with the NRC, as applicable, an appropriate analysis of any such change on facility safety, and/or an analysis of any such change on the environmental impacts and on the overall cost-benefit balance for facility operation set forth in the Final Environmental Statement and a request for an amendment to the operating license, if required by the Commission's regulations. As used in this Condition 3.(d), Final Environmental Statement means the NRC Staff Final Environmental Statement related to Operation of Peach Bottom Atomic Power Station Units Nos. 2 and 3 dated April 1973, as modified by (1) the Initial Decision of the Atomic Safety and Licensing Board dated September 14, 1973, (2) the Supplemental Initial Decision of the Atomic Safety and Licensing Board dated June 14, 1974, (3) the Decision of the Atomic Safety and Licensing Appeal Board dated July 5,1974, (4) the Memorandum and Order of the Commission dated August 8, 1974, (5) any further modification resulting froni further review by the Appeal Board and by Page 4 Amendment No. 32, $2, 201 1
the Commission, if any, and (6) any Environmental Impact Appraisal which has been or may be issued by the NRC since the FES was published in April 1973.
4.
This license is effective as the date of issuance and shall expire at midnight on July 2, 2014.
FOR THE ATOMIC ENERGY COMMISSION Original Signed by Roger Boyd, for A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing Attachments:
Amended pages to Appendices A and B DPR-44 & DPR-56 Technical Specifications Date of Issuance: July 2, 1974 Page 5 Amendment No. 191,201
Unit 3 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3 REACTIVITY CONTROL 4.3 REACTIVITY CONTROL Acolicability:
Apolicability:
Applies to the operational Applies to the surveillance status of the control rod requirements of the control system.
rod system.
Obiective:
Ob.iective:
To assure the ability of the To verify the ability of the control rod system to control rod system to control reactivity.
control reactivity.
Soecification:
Soecification:
A. Reactivity Limitations A. Reactivity Limitations
- 1. Reactivity marain -
- 1. Reactivity marain -
core loadina core loadina A sufficient number of control Sufficient control rrds shall rods shall be operable so be withdrawn followiag a that the core could be made refueling outage when core subcritical in the most alterations were performed to reactive condition during the demonstrate with a margin of operating cycle with the 0.38%4k/k that the core can strongest control rod fully be made subcritical at any withdrawn and all other time in the subsequent fuel operable control rods fully cycle with the analytically inserted.
determined strongest operable control rod fully withdrawn and all other operable rods fully inserted.
- 2. Reactivity marain -
- 2. Reactivity marain -
inoperable control rods inocerable control rods a.
Control rods which cannot a.
Each partially or fully be moved with control rod withdrawn operable control drive pressure shall be rod shall be exercised one considered inoperable.
notch at least once each week when operating above If a partially or fully the RWM low power setpoint.
withdrawn control rod drive Each partially or fully cannot be moved with drive withdrawn operable control or scram pressure the rod shall be exercised at reactor shall be brought i
least one notch within 24 to a shutdown condition hours when operating above within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> unless the RWM low power setpoint if there are three Amendment No. 16, 43, 153, 201
Unit 3
~
PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3.A Reactivity Limitations 4.3.A Reactivity limitations (Cont'd)
(Cont'd) f.
Inoperable control rods shall be positioned such that specification 3.3.A.1 is met.
In addition, during reactor power operation, no more than one control rod in any 5 x 5 array may l
be inoperable (at least 4 operable control rods must separate any 2 inoperable ones).
If this Specification cannot be met the reactor shall not be started, or if at power, the reactor shall be brought to a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B.
Control Rods 1.
Each control rod shall be B. Control Rods coupled to its drive or completely inserted and the
- 1. The coupling integrity shall control rod directional be verified for each withdrawn control valves disarmed control rod as follows:
electrically except as in 3.3.B.I.a.
This requirement
- a. When a rod is withdrawn does not apply in the refuel the first time after each condition when the reactor refueling outage or after is vented. Two control maintenance, observe discernible rod drives may be removed response of the nuclear as long as Specification 3.3.A.1 instrumentation and rod is met.
position indication for the " full-in" and " full-out"
- a. For control rod 54-35, for position.
However, for initial the remainder of cycle 10 (to rods when response is not be completed before 10/30/95).
discernible, subsequent exercising of these rods after If coupling cannot be the reactor is above the Rod Worth accomplished, the uncoupled control Minimizer low power setpoint rod may be withdrawn when 210%
shall be performed to verify of rated thermal power instrumentation response.
{
only if all the following conditions are satisfied:
- b. When the rod is fully withdrawn the first time
- 1) no other uncoupled control after each refueling outage rod is withdrawn; or after maintenance observe that the drive does not go
- 2) the uncoupled control rod to the overtravel position.
may not be withdrawn past notch position 46.
-101-Amendment No. IS, //3, U 3, 766, 187, 201 l
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m
~
Unit 3 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.4 STANDBY LIOUID CONTROL SYSTEM 4.4 STANDBY L W ID CONTROL SYSTEM (Cont'd)
\\ Cont'd) 2.
Manually initiate one of the Standby Liquid Control System Pumps and pump demineralized water into the reactor vessel from the test tank.
This test checks explosion of the charge associated with the tested loop, proper operation of the explosive valves, and pump operability. The replacement charge for the explosive valve shall be from the same manufactured batch as the one fired or from another batch which has been certified by having one of the batch successfully fired.
3.
Both systems, including both explosive valves, shall be tested in the course of two operating cycles.
B.
Normal System Reauirements B.
Normal System Reauirements At all times when the Standby Liquid Control System is required to be operable, the following conditions shall be met:
1.
At least 162.7 lbm Boron-10 1.
Boron-10 Quantity: At least once must be stored in the Standby per month calculate and record Liquid Control Solution Tank the quantity of Boron-10 stored and be available for injection.
in the Standby Liquid Control Solution Tank, t
2.
The sodium pentaborate 2.
Concentration: At least once solution concentration must per month check and record.
l be equal to or less than Also, check concentration 9.82% weight.
anytime water or boron is added to the solution.
]
-116-Amendment No. #7,,126,201
j Unit 3 J
PBAPS l
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.4 STANDBY LIQUID CONTROL SYSTEM 4.4 STANDBY LIOUID CONTROL SYSTEM (Cont'd)
(Cont'd) 3.
The Standby Liquid Control System conditions must satisfy the following equation:
[13%wt.j[(86gpmj\\[19.8%atomjh1 C
h 0
E
(
g
- where, C-Sodium Pentaborate Solution Concentration (% weight)
Q-Pump Flow Rate (gpm) 3.
Pump Flow Rate: At least against a system head of 1
once per 92 days each pump 1225 psig.
loop shall be functionally tested by pumping boron solution to the test tank.
At least once per quarter check and record pump flow rate against a system head of 1225 psig.
E-Boron-10 Enrichment (% atom 4.
Enrichment:
Following each Boron-10) addition of boron to the solution tank, calculate enrichment within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Verify results by analysis within 30 days.
5.
Solution Volume: At least once per day check and record.
-117-Amendment No. 126, 201 I
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f Unit 3 PBAPS 6.5.2 Nuclear Review Board Function 6.5.2.1 The Nuclear Review Board (NRB) shall function to provide independent review and audit of designated activities in the area of:
- a. nuclear power plant operations
- b. nuclear engineering
- c. chemistry and radiochemistry
- d. metallurgy E. instrumentation and control
- f. radiological safety
- g. mechanical and electrical engineering
- h. quality assurance practices The members of the NRB will be competent in the area of quality assurance practice and cognizant of the Qur.lity Assurance requirements of 10 CFR 50, Appendix B.
Additionally, they will be cognizant of the corporate Quality Assurance Program and will have the corporate Quality Assurance organization available to them.
Oroanization 6.5.2.2 The Chairman, members and alternate members of the NRB shall be appointed in writing by the Executive Vice President - Nuclear, and shall have an academic degree in an engineering or physical science field and in addition, shall have a minimum of five years technical experience, of which a minimum of three years shall be in one or more areas given in 6.5.2.1.
The NRB shall be composed of at least five members who are PECO Energy Company (PECO) employees and at least two outside members who are not PEC0 employees.
-249-Amendment No. 10, 37, $$, 62, 68, IIS, 135, 160, 201 l
l l
Unit 3 PBAPS 6.9.1 Routine Reports (cont'd) c.
Annual Safety / Relief Valve Reoort Describe all challenges to the primary coolant system safety and relief valves. Challenges are defined as the automatic opening of the primary coolant safety or relief valves in response to high reactor pressure.
d.
Monthly Ooeratina Reco,-t Routine reports of operating statistics and shutdown experience and a narrative summary of the operating experience shall be submitted on a monthly basis.
Each report shall be submitted no later than the 15th of the month following the calendar month covered by the report.
e.
Core Ooeratino limits Report (1) Core operating limits shall be established and shall be documented in the CORE OPERATING LIMITS REPORT prior to each Operating Cycle, or prior to any remaining portion of an Operating Cycle, for the following:
a.
The AFLHGR for Specification 3.5.I, b.
The MCPR for Specification 3.5.K, c.
The core flow and power adjustment factors for Specification 3.5.K and 3.5.I, d.
The LHGR for Specification 3.5.J, e.
The upscale power biased Rod Block Monitor setpoints and corresponding power levels.
(2) The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents as amended and approved:
a.
NEDE-24011-P-A, " General Electric Standard Application for Reactor Fuel" (latest approved version) b.
" Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Peach Bottom Atomic Power Station Units 2 and 3," NEDC-32162P, Revision 1, February, 1993 c.
PECO Energy Company Methodologies as described l
in:
(1)
PECo-FMS-0001-A, " Steady-State Thermal Hydraulic Analysis of Peach Bottom Units 2 and 3 using the FIBWR Computer Code"
-256-Amendment No, yQ), 173, y)), y@7, JS),
201
l c
4 Unit 3 PBAPS 6.0 Environmental Surveillance and Special Study Proarams Studies described in this section will be terminated upon agreement by PECO Energy Company and the Nuclear Regulatory Commission i
that the intended purpose of the study has been satisfied.
6.1 (Deleted) 6.2 (Deleted) 6.3 (Deleted) Note: Pages 15-47 l
have been deleted.
The next page is 48.
l Amendment No. 66, 94, 201
.