ML19257A643
| ML19257A643 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/12/1979 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19257A644 | List: |
| References | |
| NUDOCS 8001070103 | |
| Download: ML19257A643 (17) | |
Text
.
aasegg 70, UNITED STATES e
E ^ ', e r [ j NUCLEAR REGULATORY COMMISSION 5s
/, E WASHINGTON, D. C. 20555 o
DUQUESNE LIGFT C0f.:PANY OHIO EDISON COMPANY PENNSYLVANIA POWER COPPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT N0. 1 AP.ENDMENT TO FACILITY OPERATING LICENSE Amendment No. 23 License No. DPR-66 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company (the licensees) dated March 22, 1977 as supplemented April 11, June 23, and November 17, 1977, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Cormission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authori::ed by this amendment can be conducted without encangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Ccmission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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.
1692 113 8001070 2.
Accordingly, the 1icense is amended by changes to the Technical Specifications as indicated in the attacnnent to this license amencuent, and paragraph 2 C.(2) of Facility Operating License No. CPR-66 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 23, are hereby incorporated in the license. The licensee shall o;:erate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
[t dW$U A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Peactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 12, 1979 1692 114 m
MTACHMENT TO LICENSE AMENDMENT NO.23 FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
Pages VIII 3/4 6-19c 3/4 6-19d 3/4 9-3 3/4 9-4 3/4 9-6 3/4 9-9 3/4 9-13 B 3/4 9-1 B 3/4 9-2 B 3/4 9-3 1692 115
INDEX i
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE SECTION 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Valves..........................................
3/4 7-1 Auxil ia ry Feedwater Pumps.............................
3/47-5 Primary Plant Demin eralized Water......................
3/4 7-7 Activity...............................................
3/4 7-8 Main Steam Li ne Is ol ation Va1 ves.......................
3/4 7-10 Secondary Water Chemistry..............................
3/4 7-10a 3/4.7.2 STEAM GENERATOR PRESSURE /TEMPEPATURE LIMITATION........
3/4 7-1I 3/4.7.3 COMPONENT COOLING WAT ER SYSTEM.........................
3/4 7-12 3/4.7.4 RIVER WATER SYSTEM.....................................
3/4 7-13 3/4.7.5 U LT IM AT E H E AT S I N K.....................................
3/4 7-14 3/4.7.6 FLOO D P ROT ECT I O N.......................................
3/4 7-15 3/4.7.7 CONTROL ROOM EMERGENCY HABITABILITY SYSTEMS............
3/4 7-16 3/4.7.8 SUPPLEMENTAL LEAK COLLECTION AND RELEASE SYSTEM........
3/4 7-19 3/4.7.9 SEALED SOURCE CONTAMINATION............................
3/4 7-22 3/4.7.10 RESIDUAL HEAT REMOVAL SYSTEM T,yg >_ 350* F..............
3/4 7-24 3/4.7.11 RESIDUAL HEAT REMOVAL SYSTEM T,yg < 350*F..............
3/4 7-25 3/4.7.12 HYDRAULIC SNUBBERS.....................................
3/4 7-26 3/4.7.13 AUXILIARY RIVER WATER SYSTEM...........................
3/4 7-34 3/4.7.14 FIRE SUPPRESSI0h SYSTEMS Fi re Su p pres si on Wa t er Sys t em..........................
3/4 7-35 S p r i n kl er Sys t ems......................................
3/4 7-39 Low Pressure CO System................................
3/4 7-41 2
Fire Hose Stations............
3/4 7-42 3/4.7.15 PENETRATION FIRE 3ARRIERS.............................
3/4 7-44 1692 116 BEAVER VALLEY - UNIT 1 VII Ameninent No. g, g,11
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS
-l 3/4.8 ELECTRICAL POWER SYSTEMS 1
na 3/4.8.1 A.C. SOURCES 0 pe r a ti n g..............................................
3/4 8-1 Shutdown...............................................
3/4 8-5 3/4.8.2 ONSITE' POWER DISTRIBUTION SYSTEMS A. C. Di stri buti on - Operati ng..........................
3/4 8-6.
A.C. Distribution - Shutdown...........................
3/4 8-7
- 0. C. Di s tribution - Operating..........................
3/4 8-8 0.C. Distribution - Shutdown...........................
3/4 8-10 3/4.9 REFUELING OPERATIONS 3/4.9.1 B O RON C ON C ENT RAT I ON....................................
3/49-1 3/4.9.2 INSTRUMENTATION........................................
3/4 9-2 3/4.9.3 DECAY TIME.............................................
3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS......................
3/4 9-4 3/4.9.5 COMMUNICATIONS.........................................
3/4 9-5 3/4.9.6 MANIPULATOR CRANE OPERABILITY..........................
3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING........
3/4 9-7 3/4.9.8 COOLANT CIRCULATION....................................
3/4 9-8 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM.........
3/4 9-9 i,
i 1692 117 3EAVER VALLEY - UNIT 1 VIII Amendment No. 23
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TABLE 3.6-1 (Continued)
ISOLATION TIME y
VALVE NUMBER TESTABLE DURING (Sec)
INSIDE/0UTSIDE FUNCTION PLANT OPERATION INSIDE/0UTSIDE y>
[
- 19.
M0V-RW105A Rivemater from Recirc. Spray fix Yes N/A N/A,
- 20.
MOV-RW105C Riverwater from Recirc. Spray lix Yes N/A N/A e
- 21.
MOV-RW105B Riverwater from Recirc. Spray lix
'Yes N/A N/A sE
- 22.
MOV-RW105D Riverwater from Recirc. Spray lix Yes N/A N/A 23.
1SI-83 M0V-SI869A liiQ flead SI to llot Leo No N/A N/A 24.
15I-84 MOV-SI869B llegh llead SI to llot Leg No N/A N/A m
25.
MOV-S1890A low llead SI No N/A N/A 26.
MOV-SI890C Low llead SI No N/A N/A P7.
!!0V-SI890B Low Ilead SI No N/A N/A 78.
1SI-95 MOV-SI836 Ninh llead SI to Cold Legs No N/A N/A 79 MOV-SIB 60A Low Ilead SI Pump Suction from Cont. Sump Yes N/A N/A 30.
MOV-SI860B Low Ilead SI Pump Suction from Cont. Sump Yes N/A N/A
- 31.
1C11-170 FCV-Clll60 RCS Fill No N/A N/A 2
- 32.
1S1-41 SIAccumulator Makeup Yes N/A N/A m
33.
1 Ril-14 1 Ril-15 RilR to RWST Yes N/A N/A
- 34. IICV-CV-151 IICV-CV-151-1 Containment Vacuum Eiector Suction Yes N/A N/A g
35.
lPC-9 IPC-10 Reactor Cavity Purification - Inlet Yes N/A N/A 36.
1PC-37 IPC-38 Reactor Cavity Purification - Outlet Yes N/A N/A 37.
1SA-14 Compressed Air to Fuel llandling Equipment Yes N/A N/A 38.
IIA-90 Instrument Air No N/A N/A
- 39.
1-RC277 Press Dead Weight Calibrator Yes N/A N/A 1-RC278[M(2)1 40.
lily-lli ll Recombiner Discharge to Containment Yes N/A N/A k
41.
lily-110 11 Recombiner Discharge to Containment Yes N/A N/A
=
42.
D leted k
- 43.
MOV-MS-105 Steam to Aux. Feed Pump Yes N/A N/A
&w 44.
Deleted
=
N 45.
Deleted z
P 46.
1CV-36 Containment Leakage Monitoring - Scaled Yes N/A N/A System y
]
47.
lily-102 Cont. Vaccum Pump A 11 Recomb. Suct.
Yes N/A N/A M
lily-104 48.
lily-101 Cont. Vacuum Pump A 11 Recomb. Suct.
Yes N/A N/A lily-103 g
REFUELING OPERATIONS DECAY TIME LIMITING CONDITION FOR OPERATION 3.9.3 The reactor shall be subtritical for at least 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br />.
APPLICABILITY: During movement of irradiated fuel in the reactor pressure vessel.
ACTION:
With the reactor subcritical for less than 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br />, suspend all opera-tions involving cbvement of irradiated fuel in the reactor pressure vessel. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.3 The reactor shall be determined to have been subcritical for at least 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> by verification of the date and time of subcriticality prior to mover,:?nt of irradiated fuel in the reactor pressure vessel.
BEAVER VALLEY - UNIT 1 3/4 9-3 Amendment No. 23 1692 120
REFUELING OPERATIONS CONTAINMENT BUILDING PENETRATIONS LIMITING CONDITION FOR OPERATION 3.9.4 The containment building penetrations shall be in the following status:
a.
The equipment door closed and held in place by a minimum of four bolts, b.
A minimum of one door in each airlock is closed, and c.
Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:
1.
Closed by an isolation valve, blind flange, or manual valve, or 2.
Exhausting at less than or equal to 7500 cfm through OPERABLE Containment Purge and Exhaust Isolation Valves to OPERABLE HEPA filters and charcoal adsorbers of the Supplemental Leak Collection and Release System (SLCRS).
APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within the containment.
ACTION:
With the requirements of the above specification not satisfied, inTnedi-ately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.4.1 Each of the above required containment penetrations shall be determined to be in its above required condition within 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS or movement of irradiated fuel in the containment.
4.9.4.2 The containment purge and exhaust system shall be demonstrated OPERABLE by:
a.
Verifying the flow rate through the SLCRS at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the system is in operation.
b.
Testing the Containment Purge and Exhaust Isolation Valves per the applicable portions of Specification 4.6.3.1.2, and c.
Testing the SLCRS per Specification 4.7.8.1.
SEAVER VALLEY - UNIT 1 3/4 9-4 Amendment No.
1692 121
REFUELING OPERATIONS COMMUNICATIONS LIMITING CONDITION FOR OPERATION 3.9.5 Direct communications shall be maintained between the control room and personnel at the refueling station.
APPLICABILITY: During CORE ALTERATIONS.
ACTION:
When direct communications between the control room and personnel at the refueling station cannot be maintained, suspend all CORE ALTERATIONS.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.5 Direct communications between the control room and personnel at the refueling station shall be demcnstrated within one hour prior to the start of and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during CORE ALTERATIONS.
BEAVER VALLEY - UNIT 1 3/4 9-5 1692 122
REFUELING OPERATIONS MANIPULATOR CRANE OPERABILITY LIMITING CONDITION FOR OPERATION
[
3.9.6 The manipulator crane and auxiliary hoist shall be used for move-t ment of control rods or fuel assemblies and shall be OPERABLE with:
a.
The manipulator crane used for movement of fuel assemblies havino:
1.
A minimum capacity of 3250 pounds, and 2.
An overload cut off limit < 2850 pounds.
b.
The auxiliary hoist used for movement of control rods having:
1.
A minimum capacity of 700 pounds, and 2.
A load indicator which shall be used to prevent lifting loads in excess of 600 pounds.
APPLICABILITY: During movement of control rods or fuel assemblies within the reactor pressure vessel.
ACTION:
With the requirements for crane and/or hoist OPERABILITY not satisfied, suspend use of any inoperable manipulator crane and/or auxiliary hoist from operations involving the movement of control rods and fuel assemblies within the reactor pressure vessel. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REOUIREMENTS 4.9.6.1 Each manipulator crane used for movement of fuel assemblies within the reactor pressure vessel shall be demonstrated ODERABLE within 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> prior to the start of such operations by performino a load test of at least 3250 pounds and demonstratina an automatic load cut off when the crane load exceeds 2850 pounds.
4.9.6.2 Each auxiliary hoist and associated load indicator used for move-ment of control rods within the reactor pressure vessel shall be demonstrated ODERABLE within 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> prior to the start of such ooerations by performina a load test of at least 700 pounds.
BEAVER VALLEY-UNIT 1 3/4 9-6 Amendment No. 23 1692 123
REFUELING OPERATIONS CONTAINMENT PURGE AND EXHAUST ISOLATI0'i SYSTEM LIMITING CONDITION FOR OPERATION 1
3.9.9 The Containment Purce and Exhaust isolation system shall be OPERABLE.
APPLICABILITY: MODES 5 and 6.
ACTION:
With the Containment Purge and Exhaust isolation system inoperable, close each of the purge and exhaust eenetrations providino direct access from the containment atmosphere to the outside atmosphere.
The provisions of Specification 3.0.3 are nc applicable.
SURVEILLANCE REOUIREMENTS 4.9.9 The Containment Purge and Exhaust isolation system shall be demonstrated OPERABLE within 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> prior to the start of and at least once per 7 days durina CORE A'_TERATIONS by verifyina that contain-ment Purae and Exhaust isolation oc:urs on manual initiation and on a high-hiah radiation signal from eac'- of the containment radiation monitorina instrumentation channels.
1692 124 BEAVER VALLEY - UNIT 1 1/4 9-9 Amendment No. 23
REFUELING OPERATIONS WATER LEVEL - REACTOR VESSEL, LIMITING CONDITION FOR OPERm 10N 3.9.10 As a minimum, 23.0 feet of water shall be naintained over the top of irradiated fuel assemblies seated within the reactor pressure vessel.
APPLICABILITY: During movement of fuel assemblies or control rods within the reactor pressure vessel while in MODE 6.
ACTION:
With the requirements of the above specification not satisfied, suspend all operations involving movement of fuel assemblies or control rods within the pressure vessel. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.10 The water level shall be determined to be at least its minimum required depth within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the ', tart of and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter during movement of fuel assemblies or control rods.
BEAVER VALLEY - UNIT 1 3/4 9-10 1692 125
REFUELING OPERATIONS FUEL BUILDIN" VENT kATION SYSTEM - FUEL STORAGE i
LIMITIN3 CONDITION FOR OPERATION w
i1 3.9.13 The fuel building ventilation system shall be OPERABLE.
APPLICASILITY: WHENEVER IRRADIATED FUEL IS IN THE STORAGE POOL.
ACTI0'i:
With no fucl buildina ventilation system OPERABLE, suspend all coerations involving movement of fuel within the storage cool or crane operation with loads over the storage pool until at least one fuel building ventilation system is restored to OPERABLE status. The previsions of Specification 3.0.3 are not applicable.
SURVEILLANCE __REOUIREMENTS 4.9.13 The fuel building ventilation system shall be demonstrated OPERABLE:
a.
At least once per 31 days by initiating flow through the fuel building ventilation system and verifying that the system operates for at least 15 minutes, and b.
At least once per 18 months by:
1 1.
Verifyina that on a hich-hich radiation sional, the system automatically directs its exhaust flow through the l
HEPA filters and enarcoal adsorber banks of the Sucole-mental Leak Collection and Release System (SLCRS).
2.
Verifyinc that the ventilation system maintains the spent fuel storace pool area at a necative pressure of > 1/4 inches Water Gauge relative to the outside atmosphere durina system operation.
Testinc the SLCRS per Specification a.7.R.l.
BEAVED VALLEY - UNIT 1 3/4 9-13 Amendment Nc. 23 i
j 1692 126
3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 BORON CONCENTRATION The limitations on minimum boron concentration (2000 ppn) ensure that: 1) the reacter will remr.in subcritical during CORE ALTERATIONS, and 2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel. The limitation on K of no' greater than 0.95 which includes a conservative allowance for u,nkkrtanties, is sufficient to prevent reactor criticality during refueling operations.
3/4.9.2 INSTRUMENTATION The OPERABILITY of the source range neutron flux monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.
3/4.9.3 DECAY TIME The minimum requirement for reactor suberiticality prior to move-ment of irradiated fuel assemblies in the reactor vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products. This decay time is consistent with the assump-tions used in the accident analyses.
3/4.9.4 CONTAINMENT PENETRATIONS The requirements on containment penetration closure and OPERABILITY of the containment purge and exhaust system HEPA filters and charcoal adsorbers ensure that a r lease of radioactive material within contain-nent will be restricted from leakage to the environment or filtered through the HEPA filters and charcoal adsorbers prior to discharge to the atmo-sphere. The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based Jpon the lack of containment pressurization potential while in the REFUELING MODE. Operations of the containment purge and exhaust system 4 EPA filters and charcoal adsorbers and the resulting iodine removal
- asacity are consistent with the assumptions of the accident analyses.
EEAVER VALLEY - UNIT 1 B 3/4 9-1 Amendment No. 23 1692 127
REFUELING OPERATIONS BASES 3/4.9.5 COMMUNICATIONS The requirements for corrrnunications capability ensures that re-fueling station personnel can be promptly informed of significant changes in the facility status or core reactivity conditions during CORE ALTERATIONS.
3/4.9.6 MANIPULATOR CRANE OPERABILITY The OPERABILITY requirements for the manipulator cranes ensure that: 1) manipulator cranes will be used for movement of control rods and fuel assemblies 2) each crane has sufficient load capacity to lift a control rod or fuel assembly and 3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.
3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel assembly over other fuel assemblies ensures that no more than the contents of one fuel assembly will be ruptured in the event of a fuel handling accident. This assumption is consistent with the activity release assumed in the accident analyses.
3/4.9.8 COOLANT CIRCULATION The OPERABILITY of one residual heat removal loop ensures that sufficient cooling capacity is available to remove decay heat. This requirement is sufficient to maintain the water in the reactor pressure vessel below 140 F as required during the REFUELING MODE.
3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment vent and purge penetrations will be automatically isolated upon detection of high radiation levels within the containmment. The integrity of the containment penetrations of this system is required to restrict the release of radioactive material from the containment atmosphere to acceptable levels which are less than those listed in 10 CFR 100.
Applicability in MODE 5, although not on NRC safety requirement, will provide additional protection against small releases of radioactive material trom the containment during maintenance activities.
BEAVER VALLEY - UNIT 1 B 3/4 9-2 Amencment No. 23 1692 128
RE:UELING OPERATIONS BASES 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VE5SEL 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 released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the accident analysis.
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 analyses.
l 1692 129 EEAVER VALLEY - UNIT 1 B 3/4 9-3 Amenc ent No. 23 I
l
.