ML20237A379
| ML20237A379 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/06/1998 |
| From: | Capra R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20237A381 | List: |
| References | |
| NUDOCS 9808140013 | |
| Download: ML20237A379 (14) | |
Text
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k UNITED STATES s
j NUCLEAR REGULATORY COMMISSION 1
WASHINGTON, D.C. 30888-0XM l
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PUBLIC SERVICE ELECTRIC & GAS COMPANY I
PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.213 License No. DPR-70 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric & Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated November 14,1997, complies with the standards and requi.Tments 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 assuranco: (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 set forth in 10 CFR ChapterI; 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 l
License No. DPR-70 is hereby amended to read as follows:
l 9808140013 980806 PDR ADOCK 05000272 PDR P
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2-(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 213, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION htd (. buc GM Robert A. Capra, Director Project Directorate 1-2 Division of Reactor Projects - t/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date ofissuance: August 6,1998
ATTACHMENT TO LICENSE AMENDMENT NO. 213 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-2Z2 Revise Appendix A as follows:
' Remove Paoes InsM Paces 3/4 6-1 3/4 6-1 3/4 6-11a 3/4 6-11a B 3/4 6-1 8 3/4 S 1 B 3/4 6-3 B 3/4 6-3 l
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3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CL:STAINMENT I
CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY: MODES 1, 2, 3 and 4. **
I ACTION:
Nithout primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least MOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
l SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated i
l a.
At least once per 31 days by verifying that l
1 1.
All penetra!Lons* not capable of being closed by OPERABLE t
containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their j
l positions, except for valves that are opened under
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administrative control as permitted by specification 3.6.3.1.,
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and 2.
All equipment hatches are closed and sealed.
b.
By verifying that each containment air lock is OPERABLE per specification 3.6.1.3.
1 c.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the surveillance requirements of 4.6.2.3.a are met for penetrations associated with the containment fan coil units.
d.
At least once per 18 months by verifying that the surveillance requirements of 4.6.2.3.d are met for penetrations associated with the containment fan coil units.
- Except vents, drains, test connections, etc. which are (1) one inch nominal pipe diameter or less, (2) located inside the containment, and (3) locked, sealed, or otherwise secured in the closed position. These penetrations shall be verified closed at least once per 92 days.
- A one-time change is granted to have the containment purgo supply and/or exhaust isolation valves open in Modes 3 and 4 following the steam generator replacement outage (1R13). The cumulati e time for having the valves open in Modes 3 and 4 is limited to fourteen (14) days.
Each valve will be immobilized in the shut position prior to initial entry into Mode 2.
The one-time exemption expires with initial entry into Mode 2 following 1R13.
SALEM - UNIT 1 3/4 6-1 Amendment No. 213
s CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 1 a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:
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- 1. Verifying the water level in each service water accus.ulator vessel is greater than or equal to 226 inches and less than or equal to 252 inches.
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- 2. Verifying the temperature in each service water accumulator vessel is greater than or equal to 55'F and less than or equal to 95*F.
- 3. Verifying the nitrogen cover pressure in each service water accumulator vessel is greater than or equal to 135 psig and less than or equal to 160 psig.
b.
At least once per 31 days by:
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1.
Starting (unless already operating) each fan from the control room in low speed.
2.
Verifying that each fan operates for at least 15 minutes in low speed.
3.
Verifying a cooling water flow rate of greater than or equal e
to 2550 gym to each cooler.
c.
At least once per 18 months by verifying that on a safety l
injection test signal:
1.
Each fan starts automatically in low speed.
2.
The automatic valves and dampers actuate to their correct positions and that the cooling water flow rate to each cooler is greater than or equal to 2550 gym.
d.
At least once per 18 unths by verifying that on a loss of offsite power test signal, each service water accumulator vessel discharge valve response time !s within limits.
SALEM - UNIT 1 3/4 6-11a Amendment No. 213'
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3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses. This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.
The service water accumulator sessel and discharge valves function to maintain water filled, subcooled fluid conditions in the containment fan coil unit (CFCU) cooling loops during accident conditions. The service water accumulator vessel and discharge valves were installed to address the Generic Letter 96-06 issues of column separation waterhammer and two phase flow during an accident involving loss of offsite power. The operability of each service water accumulator vessel and discharge valve is required to ensure the integrity of containment penetrations associated with the containment fan coil units during accident conditions.
If a service water accumulator vessel does not meet the vessel surveillance requirements, or if the discharge valve response time does not meet design acceptance criteria when tested in accordance with procedures, the containment integrity requirements of the CFCU cooling loops exclusively supplied by the inoperable accumulator vessel or discharge valve are not met.
Limiting condition for Operation 3.6.1.1 is applicable, and the cooling loops for the two CFCU's exclusively supplied by the inoperable accumulator are to be removed from service and isolated to maintain containment integrity.
3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident l
analyses at the accident pressure, Pa. As an added conservatism, the measured overall integrated leakage rate (Type A test)is further limited to 5 0.75 L. or 5 0.75 L.,
as applicable, during performance of the periodic test to account for possible degradation of the containment leakage barriers between leakage tests.
The surveillance testing for measuring leakage rates is consistent with the Containment Leakage Rate Testing Program.
l 3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and the Containment Leakage Rate Testing Program. Surveillance testing of the air lock seals provide assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.
SALEM - UNIT 1 3 3/4 6-1 Amendment No. 213 l
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CONTAINMENT SYSTEMS BASES 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 CONTAINMENT SPRAY SYSTEM The OPERABILITY of the containment spray system ensures that containment depressurization and cooling capability will be available in the event of a LOCA. The pressure reduction and resultant lower containment leakage rate are consistent with I
the assumptions used in the accident analyses.
l 3/4.6.2.2 SPRAY ADDITIVE SYSTEM The OPERABILITY of the spray additive system ensures that sufficient NaOH is j
added to the containment spray in the event of a LOCA. The limits on NaOH minimum volume and concentration, ensure that 1) the iodine removal efficiency of the spray water is maintained because of the increase in pH value, and 2) corrosion effects on components within containment are minimized. The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics. These assumptions are consistent with the iodine removal efficiency assumed in the accident analyses.
g4.6.2.3 CONTAINMENT COOLING SYSTEM The OPERABILITY of the containment cooling system ensures that adequate heat removal capacity is available when operated in conjunction with the containment spray systems during post-LOCA conditions.
The surveillance requirements for the service water accumulator vessels ensure I
each tank contains sufficient water and nitrogen to maintain water filled, subcooled fluid conditions in three containment fan coil unit (CFCU) cooling loops in response to a loss of offsite power, without injecting nitrogen covergas into the containment fan coil unit loops assuming the most limiting single failure. The surveillance requirement for the discharge valve response time test ensures that on a loss of offsite power, each discharge valve actuates to the open position in accordance with the design to allow sufficient tank discharge into CFCU piping to maintain water filled, subcooled fluid conditions in three CFCU cooling loops, assuming the most
)
limiting single failure.
3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment. Containment isolation within the time limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.
The opening of locked or sealed closed containment isolation valves on an intermittent basis under administrative control includes the following considerations:
(1) stationing a dedicated individual, who is in constant communication with the control room, at the valve controls, (2) instructing this individual to close these valves in an accident situation, and (3) assuring that environmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment.
SALEM - UNIT 1 B 3/4 6-3 Amendment No. 213 l
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15 UNITED STATES j
NUCLEAR REGULATORY COMMISSION 2'
WAsMINGToN, D.C. 30086 4001 49.....,o 4
l PUBLIC SERVICE ELECTRIC & GAS COMPANY l
PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING L,;ENSE Amendment No.193 l
License No. DPR-75 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric E Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated November 14,1997, complies with the l
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 Commissien; 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 set forth in 10 CFR Chapter I; 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 l
Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated I
in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:
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2-(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 193, are hereby incorporated in the license. The licensee shall operate the facility in accoidance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION Robert A. Capra, Director Project Directorate 1-2 Division of Reactor Projects - t/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical l
Specifications
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Date of issuance: August 6,1998 l
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ATTACHMENT TO LICENSE AMENDMENT NO.193 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
Bemove Paces insert Paaes 3/4 6-1 3/4 6-1 3/4 6-13 3/4 6-13 8 3/4 6-1 B 3/4 6-1 8 3/4 6-3 8 3/4 6-3
3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY: MODES 1, 2, 3 and 4.
l ACTION:
W l
Nithout primary CONTAIKdENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD l
SHUTDONN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
- a. At least once per 31 days by verifying that all penetrations
- not
{
capable of being closed by OPERABLE containment automatic isolation 1
valves and required to be closed during accident conditions are j
closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except for valves that may be opened under Administrative control as permitted by Specification 3.6.3.1, and all equipment hatches are closed and sealed.
- b. By verifying that each containment air lock is OPERABLE per specification 3.6.1.3.
- c. After each closing of a penetration subject to Type B testing, except containment air locks, if opened following a Type A or B test, by leak rate testing in accordance with the Containment Leakage Rate Testing Program.
- d. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the surveillance requirements of 4.6.2.3.a are met for penetrations associated with the containment fan coil units.
- e. At least once per 18 months by verifying that the surveille.nce requirements of 4.6.2.3.d are met for penetrations associated with the containment fan coil units.
- Except vents, drains, test connections, etc. which are (1) one inch nominal pipe diameter or less, (2) located inside the containment, and (3) locked, sealed, or otherwise secured in the closed position. These penetrations shall be verified closed at least once per 92 days.
SALEM - UNIT 2 3/4 6-1 Amendment No.193
CONTAINMENT SYSTEMS i
SURVEILLANCE REQUIREMENTS (Continued)
=================================================================
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:
- 1. Verifying the water level in each service water l
accumulator vessel is greater than or equal to 226 l
inches and less than or equal to 252 inches.
l
- 2. Verifying the temperature in each service water accumulator vessel is greater than or equal to 55'F and less than or equal to 95'F.
- 3. Verifying the nitrogen cover pressure in each service water accumulator vessel is greater than or equal to 135 psig and less than or equal to 160 psig.
l b.
At least once per 31 days by:
l 1.
Starting (unless already operating) each fan from the control room in low speed.
2.
Verifying that each fan operates for at least 15 minutes in low speed.
3.
Verifying a cooling water flow rate of greater than er l
equal to 2550 gym to each cooler.
1 c.
At least once per 18 months by verifying that on a safety l
injection test signal:
1.
Each fan starts automatically in low speed.
2.
The automatic valves and dampers actuate to their correct l
positions and that the cooling water flow rate to each cooler is greater than or equal to 2550 gym.
d.
At least once per 18 months by verifying that on a loss of offsite power test signal, each service water accumulator vessel discharge valve response time is within limits.
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SALEM - UNIT 2 3/4 6-13 Amenda.ent No.192
3/4.6 CONTAINMENT SYSTEMS BASES
===============================================
m==========
m=====
3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses. This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR Part 100 during accident conditions.
The service water accumulator vessel and discharge valves function to maintain water filled, subcooled fluid conditions in the containment fan coil unit (CFCU) cooling loops during accident conditions. The service water accumulator vessel and discharge valves were installed to address the Generic Letter 96-06 issues of column separation waterhammer and two phase flow during an accident involving loss of offsite power. The operability of each service water accumulator vessel and discharge valve is required to ensure the integrity of containment penetrations associated with the containment fan coil units during accident conditions. If a service water accumulator vessel does not meet the vessel surveillance requirements, or if the discharge valve response time does not meet design acceptance criteria when tested in accordance with procedures, the containment integrity requirements of the CFCU cooling loops exclusively supplied by the inoperable accumulator vessel or discharge valve are not met.
Limiting condition for Operation 3.6.1.1 is applicable, and the cooling loops for the two CFCU's exclusively supplied by the inoperable accumulator are to be removed from service and isolated to maintain containment integrity.
3/4.6.1.2 CONTAINMENT LEAKAGE l
l The limitations on containment leakage rates ensure that the total
]
containment lesh. age volume will not exceed the value assumed in the accident i
analyses at the accident pressure, P,.
As an added conservatism, the measured overall integrated leakage rate (Type A test) is further limited to less than or equal to 0.75 L, or less than or equal to 0.75 L.,
as applicable, during performance of the period's test to account for possible degradation of the containment leakage barriMs tjetween leakage tests.
The surveillance testiug for measuring leakage rates are consistent with the Containment Leakage Rate Testing Program.
3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and the Containment Leakage Rate Testing Program. Surveillance testing of the air lock seals provide assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.
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SALEM - UNIT 2 B 3/4 6-1 Amendment No.193 I
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CONTAINMENT SYSTEMS BASES 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 CONTAIl@ DENT SPRAY SYSTEM The OPERABILITY of the containment spray system ensures that containment depressurisation and cooling capab.lity will be available in the event of a IOCA. The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the accident analyses.
The containment spray system and the containment cooling system are
-redundant to each other in providing post accident cooling of the containment atmosphere, sowever, the containment spray system also provides a mechanism for j
removing iodine from the containment atmosphere and therefore the time requirements for restoring an inoperable spray system to OPERABLE status have been maintained consistent with that assigned other inoperable ESF equipment.
I 3/4.6.2.2 SPRAY ADDITIVE SYSTEM The OPERABILITY of the spray additive system ensures that sufficient NaOH is added to the containment spray in the event of a LOCA. The limits on NaOH volume and conoontration, ensure that 1) the iodine removal efficiency of the spray water is maintained because of the increase in pH value, and 2) corrosion effects on components within containment are minimised. The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics. These assumptions are consistent with the iodine removal efficiency assumed in the accident analyses.
3/4.6.2.3 CONTAINMENT COOLING SYSTEM j
The OPERABILITY of the containment cooling system ensures that adequate heat i
removal capacity is available when operated in conjunction with the containment spray systems during post-I.OCA conditions.
The containment cooling system and the containment spray system are redundant to each other in providing post accident cooling of the containment atmosphere. As a result of this redundancy in cooling capability, the allowable out of service time requirements for the containment cooling system have been appropriately adjusted.
However, the allowable out of service time requirements for the containment spray system have been maintained ponsistent with that assigned other inoperable EsF equipment since the containment spray system also provides a mechanism for removing iodine from the containment atmosphere.
The surveillance requirements for the servios water accumulator vessels ensure each tank contains sufficient water and nitrogen to maintain water filled, subcooled fluid conditions in three containment fan coil unit (CFCU) cooling loops in response to a loss of offsite power, without injecting nitrogen covergas into the contai w nt fan coil unit loops assuming the most limiting single failure. The surveillance i
requirement for the discharge valve response time test ensures that on a loss of
-)
offsite power, each discharge valve actuates to the open position in accordance with l
the design to allow sufficient tank discharge into CFCU piping to maintain water j
filled, subcooled fluid conditions in three CFCU cooling loops, assuming the most
]
limiting single failure.
SALEM - UNIT 2 B 3/4 6-3 Amendment No.193 l
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