ML20012E869
| ML20012E869 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 03/21/1990 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duquesne Light Co, Ohio Edison Co, Pennsylvania Power Co |
| Shared Package | |
| ML20012E870 | List: |
| References | |
| DPR-66-A-151, NPF-73-A-028 NUDOCS 9004060480 | |
| Download: ML20012E869 (15) | |
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't UNITED 8TATES
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~g NUCLEAR REGULATORY COMMIS$10N 1
WASHINGTON, D. C. 30666
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PENNSYLVANIA POWER COMPANY DOCKET N0. 50-334 BEAVER VALLEY POWER STATION. UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 151 License No. DPR-66 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Duquesne Light Company, et al.
(the licensee) dated October 16, 1990 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter it B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities huthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulationst D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
l 9004060480 900321 PDR ADOCK 05000334 P
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license No.DPR-6$andparagraph2.C.(2)ofFacilityOperatingLicense amendment is hereby amended to read as follows:
i (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 151, 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 the date of its issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION r
J
$ o z. D ector Project Directorate 1-4 I
Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of 1ssuance: March 21, 1990 l
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ATTACW.ENT TO LICENSE AMENDMENT N0.151 l
FACILITY OPERATING LICENSE NO. OPR-66 DOCKET NO. 50-334 l
ReplacethefollowingpagesofAppendixA(TechnicalSpecifications)withthe enclosed pages as indicated. The revised pages are identif fed by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 3/4 7-34 3/4 7-34 3/4 7-19 3/4 7-19 3/4 7-22 3/4 7-22 3/4 7-23 3/4 7-23 I
B3/4 9-3 B3/4 9-3 1
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L, PLANT SYSTEMS i
3/4.7.13 AUXILIARY RIVER WATER SYSTEM l
LIMITING CONDITION TOR OPERATION 3.7.13.1 At least one auxiliary river water subsystem shall be i
APPLICABILITY MODES 1, 2, 3, and 4.
i ACTION:
With less than one ARWS subsystem OPERABLE, restore at least one subsystem to OPERABLE status within 7
days or be in at least HOT STANDBY within the next 6
hours and in COLD SHUTDOWN within the following thirty hours.
l SURVEILLANCE REQUIREMENTS
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I 4.7.13.1 At least one ARWS subsystem shall be demonstrated OPERABLE:
l a.
At-least once per 92
- days, by verifying that each pump l
develops at least 60 psig discharge pressure, while pumping through its test flow line.
b.
At least once per 18 months during shutdown by starting an Auxiliary River Water System Pump, shutting down one Reactor Plant River Water System
- Pump, and verifying that the L
Auxiliary River Water Subsystem provides at least 8000 gpm cooling water to that portion of the Reactor Plant River Water system under test for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
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l BEAVER VALLE Y - UNIT 1 3/4 7-34 Amendment No.% 151
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' PLANT SYSTEMS i
3/4.7.8 SUPPIrMENTAL fFAX CoftFCTION AND RETFASE SYSTEM (SLCRS)
LIMITING CONDITION FOR OPERATION 3.7.8.1 Two SLCRs exhaust air filter trains shall be OPERABLE.
APPLICABILITY :
MODES 1, 2,
3, and 4.
ACTION:
With one SLCRS exhaust air filter train inoperable, restore the inoperable train to OPERABLE status within 7 days or be in at least i
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 SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
i SURVEILLANCE REQUIREMENTS 4.7.8.1 Each SLCRS exhaust air filter train shall be demonstrated OPERABLE:
a.
At least once per 31 days on a STAGGERED TEST BASIS by:
L 1.
Initiating, from the control room, flow through the HEPA L
filter and charcoal adsorber train and verifying that the L
train operates for at least 15 minuten.
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b.
At least once per 12 months or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation or (1) after each complete or partial l
replacement of a
HEPA filter or charcoal adsorber bank, or (2) after any structural maintenance on the HEPA filter or charcoal adsorber
- housings, or (3) following painting, fire or chemical release in any ventilation zone communicating L
with the system by:
1 1.
Verifying that the charcoal adsorbers remove 1 99% of a halogenated hydrocarbon refrigerant test gas when they r
I are testing in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 36,000 cfm i 10%.
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l BEAVER VALLEY - UNIT 1 3/4 7-19 Amendment No.151
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PLANT SYSTEMS 3/4.7.9 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.9.1 Each sealed source containing' radioactive material either in excess of 100 microcuries of beta-and/or gamma-emitting I
material or 5 microcuries of alpha-omitting material shall be free of 2 0.005 microcuries of removable contamination.
APPLICABILITY:
At all times.
ACTION:
a.
With a
sealed source having removable contamination in excess of the above limit, immediately withdraw the sealed source from use and either:
i 1.
Decontaminate and repair the sealed source, or l
2.
Dispose of the sealed source in accordance with Commission l
Regulations.
b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.9.1.1 Test Requirements - Each sealed source shall be tested for i
leakage and/or contamination by:
a.
The licensee, or b.
Other persons specifically authorized by the Commission or an Agreement State.
The test method shall have a detection sensitivity of at least 0.005 I
microcuries per test sample, 4.7.9.1.2 Test Frequencies Each category of sealed sources (excluding startup sources and fission detectors previously subjected to core flux) shall be tested at the frequency described below.
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BEAVER VALLEY Unit 1 3/4 7-22 Amendment No. tM 151 l
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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) l n.
Sources in use - At least once per six months for all sealed sources containing radioactive materials.
1.
With a
half-life greater than 30 days (excluding Hydrogen 3) and 2.
In any form other than gas.
b.
Stored sources not in use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous six months.
Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to being placed into use.
c.
Startup sources and fission detectors - Each sealed startup source' and fission detector shall be tested within 31 days prior to being subjected to core flux or installed in the core and following repair or maintenance to the source.
4.7.9.1.3 Reports - A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 on an annual basis if sealed source or fission detector leakage tests reveal the t
presence of 2 0.005 nicrocuries of removable contamination.
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BEAVER VALLEY Unit 1 3/4 7-23 Amendment No. ++0,151 (next page is 3/4 7/26) l
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, REFUELING OPERATIONS BASES 3/4.9.10 AND 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND STORAGE POOL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity 1
released from the rupture of an irradiated fuel assembly.
The minimum l
water depth is consistent with the assumptions of the accident j
analysis.
l 3/4.9.12 and 3/4.9.13 FUEL BUILDING VENTILATION SYSTEM The limitations on the storage pool ventilation system ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere.
The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analysis.
The spent fuel pool area ventilation system is non-safety related and only recirculates air through the fuel building.
The SLCRS portion of the ventilation system is safety-related and maintains a
negative pressure in the fuel building.
The SLCRS flow is normally exhausted to the atmosphere without filtering,
- however, the flow is diverted through the main filter banks by manual actuation or on a high radiation signal.
3/4.9.14 FUEL STORAGE - SPENT FUEL STORAGE POOL The requirements for fuel storage in the spent fuel pool ensure that:
(1) the spent fuel pool will remain suberitical during fuel storage; and (2) a uniform boron concentration is maintained in the water volume in the spent fuel pool to provide negative reactivity for postulated accident conditions under the guidelines of ANSI 16.1-1975.
The value which includes all uncertainties at the of 0.95 or less for k ff 95/95 probability / conf,iden,ce level is the acceptance criteria for fuel l
storage in the spent fuel pool.
l The Action Statement applicable to fuel storage in the spent fuel pool ensures that:
(1) the spent fuel pool is protected from distortion in the fuel storage pattern that could result in a critical array during the movement of fuel; and (2) the boron concentration is maintained at 2
1050 ppm (this includes a
50 ppm conservative allowance for uncertainties) during all actions involving movement of fuel in the l
spent fuel pool.
The Surveillance Requirements applicable to fuel storage in the spent fuel pool ensure that:
(1) the fuel assemblies satisfy the analyzed t
U-235 enrichment limits or an analysis has been performed and it was i
determined that K
is 5 0.95; and (2) the boron concentration meets the 1050 ppm limit,gg The enrichment limitations for storage of fuel in a 3 of 4 array in the spent fuel pool is based on a nominal region average enrichment with individual fuel assembly tolerance of + or - 0.05 w/o U-235.
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BEAVER VALLEY - UNIT 1 B 3/4 9-3 M:endment No. TS, 442 ?H4,151
-!.ctter & tei 2/5/00 L
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UNITED $TATES
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,o NUCLE AR REGULATORY COMMISSION 5*,",.
W ASHINGTON, D, C,30666 l
t DUQUESNE LIGHT COMPANY l
OH10 EDISON COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDIS0N COMPANY DOCKET N0. 50-412 BEAVER VALLEY POWER STATION, UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 28 License No. NPF-73 1.
The Nuclear Regulatory Comission (the Commission) has found that:
l A.
The application for amendment by Duquesne Light Company, et al.
(the licensee) dated October 16, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Connission'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 i
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.
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2-2.
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. NPF-73 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 28, and the Environmental Protection Plan contained in Appendix B both of which are attached hereto are hereby incorporated in the license. DLC0 si.sil operate the facility in ac:ordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMM15510N l
12, ir$r Project Directorate 1-4 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date nf Issuance:
March 21, 1990 4
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ATTACHMENT TO LICENSE APINtiktWT NO. 28 FACILITY OPERATING LICEN$t NO. NPF-73 D0Ctti NO. 50 412 L
i Peplace the following pages of Appendix A (Technical $pecifications) with the enclosed pages as in$fcated. The revised pages are identified by amendwent nunber and contain vertical lines indicating the areas of change.
Remove Insert 3/4 7 18 3/4 7 28 3/4 7 18 3/4 7-18 3/4 7 20 3/4 7-20 3/4 7 21 3/4 7 21 l
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PLANT $Y$TEMS
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3/4.7.13 $TANDBY SERVICE WATER $YSTEM ($WE) i i
(
LIMITIMP. CoWBITIDW FOR OPrAATIDW
)
o 3.7.13.1 At least one standby service water subbystem shall be OPERABLE.
APPLICABILITY:
MODE $ 1, 2, 3. And 4.
l ACTION:
i i
With less than one $WE subsystem OPERABLE, restore at least one subsystem to OPERABLE status within 7 days or te 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 SHUTDOWN within the following thirty huurs.
SURVf1LLANtf RE001kfMfWTS i
4.7.13.1 At least one $WE subsystem shall be demonstrated OPERABLE:
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At least once per 92 days, by verifying that each pump develops at
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1 east 109 psid differential pressure, while pumping through its test i
flow line, i
b.
At least once per 18 months during shutdown by starting a Standby Service Water System Pump, shutting down one Service Water System Pump, and verifying that the Standby Service Water Subsystem provides at least 8584 gpm cooling water to that portion of the Servict 4ter j
System undar 'est for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
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BEAVER VALLEY - UNIT 2 3/4 7-28 Amendtent No. 28 i
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s PLANT SYSTEMS 4
3/4.7.8 $UPPLEMENTAL LEAK COLLECTION AND RELEA$f $Y$ TEM ($LCR$)
LIMIT 1ho 00NDIT10W TOR OPfeATION i
3.7.8.1 Two $LCR$ exhaust air filter trains sha11 be OPERABLt.
APPLICABILITY: MODE $ 1, 2, 3 and 4.
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ACTION:
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With one $LCR$ exhaust air filter train inoperable, restore the inoperable train to OPERABLE stctus within 7 days or be in at least HOT STANDBY within the l
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 iURVEILLANCE Rfou1REMENTS l
4.7.8.1 Each SLCRS exhaust air filter train shall be demonstrated OPERABLE:
r a.
At least once per 31 days by initiating, from the control room, flow i
through the " standby" HEPA filter and charcoal adsorber train and i
verifying that the train operates for at least 15 minutes with the j
heater controls operational.
i b.
At least once per 18 months or (1) after each complete or partial l
replacement of a HEPA filter or charcoal adsorber bank, or (2) after i
any structural maintenance on the HEPA filter or charcoal adsorber housings or (3) following painting, fire or chemical release in any ventilatIontonecommunicatingwiththesystemby:
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1.
Verifying that the charcoal adsorbers remove > 99.95% of a halo-i genated hydrocarbon refrigerant test gas when~they are tested in-place in accordance with ANSI N510-1980 while operating the vehtilaticn 6y6 tem 6t 6 i kw reis of 57,000 cfm f,104.
2.
Verifying that the HEPA filter banks remove > 99.95% of the 00P i
when they are tested in-place in accordance with AN$1 N510-1980 t
while operating the ventilation system at a flow rate of I
L 57,000 cfm i 10%.
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3.
Subjecting the carbon contained in at least one test canister
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or at least twc carbon samples removed from one of the charcoal adsorbers to a laboratory carbon sample analysis and verifying a l
removal efficiency of > 99% for radioactive methyl iodide at an air flow velocity of 077 ft/sec 120% with an inlet methyl iodide concentration of 1.5 to 2.0. og/m*,170% relative humidity, and 30'C 1 4*C; other test conditions shall be in accordance f
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with ANSI N510-1980.
The carbon samples not obtained from test canisters shall be taken with a slotted tube sampler in accord-I ance with ANSI N509-1980.
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BEAVER VALLEY - UNIT 2 3/4 7-18 Amendment No. %, 28 l
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PLANT SYSTEMS 3/4.7.9 $EALED SOURCE CONTAMINATION LIMITINC 00MDITf0W FOR OPERATf0W 3.7.9.1 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emittin material or 5 microcuries of alpha emitting material shall be free of 1 0.00 microcuries of removable contamination, j
APPLICABILITY:
AT ALL TIMES.
ACTION:
j 1
4.
With a sealed source having removable contamination in excess of the
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above limit, immediately withdraw the sealed source from use and either:
l 1.
Decontaminate and repair the sealed source, or 2.
Dispose of the sealed source in accordance with Commission Regulations.
l b.
The provisions of Specification 3.0.3 are not applicable.
I
$URVEILLANCE REQUIREMENTS 4.7.9.1.1 Test Requiremer.ts - Each sealed source shall be tested for leakage l
and/or contamination by:
a.
The licensee, or I
b.
Other persons specifically authorized by the Commission or an i
Agreement State.
i The test method shall have a detection sensitivity of at least 0.005 microcuries i
per test sample.
4.7.9.1.2 Test Frequencies - Each category of sealed sources (excluding I
startup sources and fission detectors previously subjected to core flux) shall be tested at the frequency described below.
s.
Sources in use - At least once per six months for all sealed sources l
l containing radioactive materials.
l 1.
With a half-life greater than 30 days (excluding Hydrogen 3) and 2.
In any form other than gas.
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BEAVER VALLEY - UNIT 2 3/4 7-20 Amendment No. 4, 28 I
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i PLANT SYSTEMS fuRVf1LLANCE REBUIREMENT1 (00W11NUfbi
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b.
Stored sources not in use - Each sealed source and fission detector l
shall be tested prior to use or transfer to another licensee unless tested within the previous six months.
Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to being placed into use.
t c.
Startup sources and fission detectors - Each sealed startup source l
and fission detector shall be tested within 31 days prior to being
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subjected to core flux or installed in the core and following repair or maintenance to the source.
l 4.7.9.1.3 Reports - A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 on an annual basis if sealed source or fission detector leakage tests reveal the presence of > 0.005 microcuries of removable contamination.
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BEAVER VALLEY - UNIT 2 3/4 7-21 Amendment No. 28
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