ML20096C988
| ML20096C988 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 01/11/1996 |
| 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 | |
| ML20096C992 | List: |
| References | |
| DPR-44-A-212, DPR-56-A-217 NUDOCS 9601180404 | |
| Download: ML20096C988 (16) | |
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UNITED STATES j
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NUCLEAR REGULATORY COMMISSION 4
2 WASHINGTON, D.C. - =1
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PECO ENERGY COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY
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l ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.212 License No. DPR-44 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by PECO Energy Company, et al. (the licensee) dated November 21, 1995, 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 (1) 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 and safety of the public; and 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, 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:
l 9601180404 960111 l
PDR ADOCK 05000277 P
1
. (2) Technical Snecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 212, are hereby incorporated in the license.
PECO Energy Company shall operate, the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and is to be implemented concurrently with Amendment 210, issued August 30, 1995.
FOR THE NUCLEAR REGULATORY COMMISSION ohn F. Stolz, Direc Project Directorate 2
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 11, 1996
_. ~ _ ~ _.
1 I
ATTACMENT TO LICENSE AMENDMENT NO. 212 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Insert 3.5-6 3.5-6 3.5-13 3.5-13 5.0-12 5.0-12 B 3.5-14 8 3.5-14 B 3.5-28 0 3.5-28
ECCS--Operating 3.5.1 SURVEILLANCE REQUIRENENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.1.8
NOTE--------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to. perform the test.
Verify, with reactor pressure s 1053 and 92 days 2 940 psig, the HPCI pump can develop a flow rate 2 5000 gpa against a system head corresponding to reactor pressure.
~
NOTE--------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.
Verify, with reactor pressure s 175 psig, 24 months the HPCI pump can develop a flow rate 2 5000 gpa against a system head corresponding to reactor pressure.
SR 3.5.1.10
NOTE--------------------
Vessel injection / spray may be excluded.
Verify each ECCS injection / spray subsystem 24 months actuates on an actual or simulated automatic initiation signal.
SR 3.5.1.11
NOTE--------------------
Valve actuation may be excluded.
Verify the ADS actuates on an actual or 24 months simulated automatic initiation signal.
(continued)
PBAPS UNIT 2 3.5-6 Amendment No.210, 212
RCIC System 3.5.3 SURVEILLANCE REQUIRENENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System piping is filled 31 days with water from the pump discharge valve to the injection valve.
SR 3.5.3.2 Verify each RCIC System manual, power 31 days operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
NOTE--------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.
Verify, with reactor pressure s 1053 psig 92 days and 2 940 psig, the RCIC pump can develop a flow rate 2 600 gpa against a system head corresponding to reactor pressure.
NOTE--------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.
Verify, with reactor pressure s 175 psig, 24 months the RCIC pump can develop a flow rate 2 600 gpa against a system head corresponding to reactor pressure.
(continued) i i
PBAPS UNIT 2 3.5-13 Amendment No. 210, 212
0 1
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Ventilation Filter Testina Proaram (VFTP)
(continued) 1)
Once per 12 months for standby service or after 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation; and, 2)
After each complete or partial replacement of the HEPA filter train or charcoal adsorber filter; after any structural maintenance on the system housing; and, following significant painting, fire, or chemical release in any ventilation zor.e communicating with the system while it is in operation.
Tests described in Specifications 5.5.7.d and 5.5.7.e shall be performed once per 24 months.
The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.
a.
Demonstrate for each of the ESF systems that an inplace test of the HEPA filters shows a penetration and system bypass
< 0.05% when tested in accordance with Regulatory Guide 1.52, Revision 2, Section Sc, and ASME N510-1989, Sections 6 (Standby Gas Treatment (SGT) System only) and 10, at the system flowrate specified below.
ESF Ventilation System Flowrate (cfm)
SGT System 7200 to 8800 Main Control Room Emergency 2700 to Ventilation (MCREV) System 3300 (continued)
PBAPS UNIT 2 5.0-12 Amendment No. 210, 212
ECCS-Operating B 3.5.1
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BASES SURVEILLANCE SR 3.5.1.7. SR 3.5.1.8. and SR 3.5.1.9 (continued)
REQUIREMENTS pressure when the HPCI System diverts steam flow.
Reactor steam pressure must be s 1053 and 2 940 psig to perform
[
SR 3.5.1.8 and greater than or equal to the Electro-Hydraulic Control (EHC) System minimum pressure set with the EHC System controlling pressure (EHC System begins controlling pressure at a nominal 150 psig) and.s 175 psig to perform SR 3.5.1.9.
Adequate steam flow is represented by at least 2 turbine bypass valves open. Therefore, sufficient time is allowed after adequate pressure and flow are achieved to perform these tests. Reactor startup is allowed prior to performing the low pressure Surveillance test because the reactor pressure is low and the time allowed to satisfactorily perform the Surveillance test is short. The reactor pressure is allowed to be increased to normal operating pressure since it is assumed that the low pressure test has been satisfactorily completed and there is no indication or reason to believe that HPCI is inoperable.
Therefore, SR 3.5.1.8 and SR 3.5.1.9 are modified by Notes that state the Surveillances are not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the reactor steam pressure and flow are adequate to perform the test.
The 92 day Frequency for SR 3.5.1.7 and SR 3.5.1.8 is consistent.with the Inservice Testing Program requirements.
The 24 month Frequency for SR 3.5.1.9 is based on the need to perform the Surveillance under the conditions that apply just prior to or during a startup from a plant outage.
Operating experience has shown that these components will pass the SR when performed at the 24 month Frequency, which is based on the refueling cycle. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.
SR 3.5.1.10 The ECCS subsystems are required to actuate automatically to perform their design functions. This Surveillance verifies that, with a required system initiation signal (actual or simulated), the automatic initiation logic of HPCI, CS, and LPCI will cause the systems or subsystems to operate as designed, including actuation of the system throughout its emergency operating sequence, automatic pump startup and actuation of all automatic valves to their required positions.
This SR also ensures that the HPCI System will (continued)
PBAPS UNIT 2 B 3.5-14 Amendment 212
RCIC Systeo B 3.5.3 l
BASES i
SURVEILLANCE SR 3.5.3.2 (continued) 4 1
REQUIREMENTS The 31 day Frequency of this SR was derived from the Inservice Testing Program requirements for performing valve testing at least once every 92 days. The Frequency of l
31 days is further justified because the valves are operated i
under procedural control and because improper valve position j
would affect only the RCIC System. This Frequency has been j
shown to be acceptable through operating experience.
t i
SR 3.5.3.3 and SR 3.5.3.4 The RCIC pump flow rates ensure that the system can maintain reactor coolant inventory during pressurized conditions with l
the RPV isolated. The flow tests for the RCIC System are performed at two different pressure ranges such that system e
i capability to provide rated flow is tested both at the i
higher and lower operating ranges of the system.
Additionally, adequate steam flow must be passing through the main turbine or turbine bypass valves to continue to j
control reactor precsure when the RCIC System diverts steam i
7 flow. Reactor steam pressure must be s 1053 and 2 940 psig
[
l to perform SR 3.5.3.3 and greater than or equal to the i'
Electro-Hydraulic Control (EHC) System minimum pressure set i
l with the EHC System controlling pressure (the EHC System j
begins controlling pressure at a nominal 150 psig) and s 175 psig to perform SR 3.5.3.4.
Adequate steam flow is represented by at least 2 turbine bypass valves open.
Therefore, sufficient time is allowed after adequate pressure and flow are achieved to perform these SRs.
Reactor startup is allowed prior to performing the low pressure Surveillance because the reactor pressure is low I
and the time allowed to satisfactorily perform the Surveillance is short.
The reactor pressure is allowed to be increased to normal operating pressure since it is assumed that the low pressure Surveillance has been satisfactorily completed and there is no indication or reason to believe that RCIC is inoperable.
Therefore, these SRs are modified by Notes that state the Surveillances are not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the reactor steam pressure and flow are adequate to perform the test.
(continued) i PBAPS UNIT 2 8 3.5-28 Amendment 212 i
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UNITED STATES g
j NUCLEAR REGULATORY. COMMISSION o
WASHINGTON, D.C. 20606 @ 01 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 NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 217 License No. DPR-56 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by PECO Energy Company, et al. (the licensee) dated November 21, 1995, 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 (1) 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 Connission'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 the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, 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-56 is hereby amended to read as follows:
4,
j (2) Technical Snecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 217, are hereby incorporated in the license. PECO shall operate the facility in accordance with the Technical Specifications.
i 3.
This license amendment is effective as of its date of issuance and is to be implemented concurrently with Amendment 214, issued August 30, 1995.
l FOR THE NUCLEAR REG LATORY COMISSION O
1 F. Stolz, Direc,o j
oject Directorate 2
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation 4
l
Attachment:
Changes to the Technical Specifications i
Date of Issuance:
January 11, 1996 i
i t
1 4
1
4 i
e ATTACMENT TO LICENSE AMENDMENT NO. 217 FACILITY OPERATING LICENSE N0. DPR-56 DOCKET NO. 50-278 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Insert 3.5-6 3.5-6 3.5-13 3.5-13 5.0-12 5.0-12 B 3.5-14 B 3.5-14 B 3.5-28 8 3.5-28
ECCS-_0perating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.1.8
NOTE--------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.
Verify, with reactor pressure s 1053 and 92 days 2 940 psig, the HPCI pump can develop a flow rate 15000 gpa against a system head corresponding to reactor pressure.
NOTE--------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.
Verify, with rsact:r pressure s 175 psig, 24 months the HPCI pues can develop a flow rate
~
2 5000 gpm against a system head corresponding to reactor pressure.
SR 3.5.1.10
NOTE--------------------
Vessel injection / spray may be excluded.
Verify each ECCS injection / spray subsystem 24 months actuates on an actual or simulated automatic initiation signal.
SR 3.5.1.11
NOTE--------------------
Valve actuation may be excluded.
Verify the ADS actuates on an actual or 24 months simulated automatic initiation signal.
(continued)
PBAPS UNIT 3 3.5-6 Amendsent No. 214, 217
')
i i
RCIC System 3.5.3 i
i SURVEILLANCE REQUIRENENTS
)
SURVEILLANCE FREQUENCY l
SR 3.5.3.1 Verify the RCIC System piping is filled 31 days with water from the pump discharge valve to the injection valve.
SR 3.5.3.2 Verify each RCIC System manual, power 31 days operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
NOTE--------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.
Verify, with reactor pressure s 1053 psig 92 days and 2 940 psig, the RCIC pump can develop a flow rate 2 600 gpa against a system head corresponding to reactor pressure.
NOTE--------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.
Verify, with reactor pressure s 175 psig, 24 months the RCIC pump can develop a flow rate 2 600 gpa against a system head corresponding to reactor pressure.
(continued)
PBAPS UNIT i 3.5-13 Amendment No214, 217
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Ventilation Filter Testina Proaram (VFTP)
(continued) e 1)
Once per 12 months for standby service or after 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation; and, 2)
After each complete or partial replacement of the HEPA filter train or charcoal adsorber filter; after any structural maintenance on the system housing; and', following significant painting, fire, or chemical release in any ventilation zone communicating with the system while it is in operation.
Tests described in Specifications 5.5.7.d and 5.5.7.e shall be j
performed once per 24 months.
The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.
a.
Demonstrate for each of the ESF systems that an inplace test of the HEPA filters shows a penetration and system bypass
< 0.05% when tetted in accordance with Regulatory Guide 1.52, Revision 2, Section Sc, and ASME N510-1989, Sections 6 (Standby Gas Treatment (SGT) System only) and 10, at the system flowrate specified below.
ESF Ventilation System Flowrate (cfm)
SGT System 7200 to 8800 Main Control Room Emergency 2700 to Ventilation (MCREV) System 3300 (continued)
PBAPS UNIT 3 5.0-12 Amendment No. 2f4, 217
s ECCS-Operating B 3.5.1 i
BASES SURVEILLANCE SR 3.5.1.7. SR 3.5.1.8. and SR 3.5.1.9 (continued)
REQUIREMENTS pressure when the HPCI System diverts steam flow.
Reactor i
steam pressure must be 5 1053 and 2 940 psig to perform I
SR 3.5.1.8 and greater than or equal to the Electro-Hydraulic Control (EHC) System minimum pressure set with the EHC System controlling pressure (EHC System begins controlling pressure at a nominal 150 psig) and s 175 psig to perform SR 3.5.1.9.
Adequate steam flow is represented I
by at least 2 turbine bypass valves open. Therefore, i
sufficient t.ime is allowed after adequate pressure and flow are achieved to perform these tests.
Reactor startup is allowed prior to performing the low pressure Surveillance test because the reactor pressure is low and the time allowed to satisfactorily perform the Surveillance test is short. The reactor pressure is allowed to be increased to normal operating pressure since it is assumed that the low pressure test has been satisfactorily completed and there is no indication or reason to believe that HPCI is inoperable.
Therefore, SR 3.5.1.8 and SR 3.5.1.9 are modified by Notes that state the Surveillances are not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the reactor steam pressure and flow are adequate to perform the test.
The 92 day Frequency for SR 3.5.1.7 and SR 3.5.1.8 is consistent with the Inservice Testing Program requirements The 24 month Frequency for SR 3.5.1.9 is based on the need to perform the Surveillance under the conditions that apply just prior to or during a startup from a plant outage.
Operating experience has shown that these components will pass the SR when performed at the 24 month Frequency, which is based on the refueling cycle.
Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.
SR 3.5.1.10 The ECCS subsystems are required to actuate automatically to perform their design functions. This Surveillance verifies that, with a required system initiation signal (actual or simulated), the automatic initiation logic of HPCI, CS, and LPCI will cause the systems or subsystems to operate as designed, including actuation of the system throughout its emergency operating sequence, automatic pump startup and actuation of all automatic valves to their required positions. This SR also ensures that the HPCI System will (continued)
PBAPS UNIT 3 8 3.5-14 Amendment No. 217
a l
RCIC Systeo B 3.5.3 BASES SURVEILLANCE SR 3.5.3.2 (continued)
REQUIREMENTS The 31 day Frequency of this SR was derived from the Inservice Testing Program requirements for performing valve testing at least once every 92 days. The Frequency of 31 days is further justified because the valves are operated under procedural control and because improper valve position would affect only the RCIC System. This Frequency has been shown to be acceptable through operating experience.
SR 3.5.3.3 and SR 3.5.3.4 The RCIC pump flow rates ensure that the system can maintain reactor coolant inventory during pressurized conditions with the RPV isolated.
The flow tests for the RCIC System are performed at two different pressure ranges su:h that system capability to provide rated flow is tested bo.n.at the 1
higher and lower operating ranges of the system.
Additionally, adequate steam flow must be passing through the main turbine or turbine bypass valves to continue to control reactor pressure when the RCIC System diverts steam i
flow.
Reactor steam pressure must be s 1053 and 2 940 psig I
to perform SR 3.5.3.3 and greater than or equal to the Electro-Hydraulic Control- (EHC) System minimum pressure set with the EHC System controlling pressure (the EHC System begins controlling pressure at a nominal 150 psig) and s 175 psig to perform SR 3.5.3.4.
Adequate steam flow is represented by at least 2 turbine bypass valves open.
Therefore, sufficient time is allowed after adequate pressure and flow are achieved to perform these SRs.
Reactor startup is allowed prior to performing the low pressure Surveillance because the reactor pressure is low and the time allowed to satisfactorily perform the Surveillance is short. The reactor pressure is allowed to be. increased to normal operating pressure since it is assumed that the low pressure Surveillance has been satisfactorily completed and there is no indication or reason to beliere that RCIC is inoperable. Therefore, these SRs are modified by Notes that state the Surveillances are not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the reactor steam pressure and flow are adequate to perform the test.
(continued)
PBAPS UNIT 3 8 3.5-28 Amendment No. 217 d
.