ML20128C843
| ML20128C843 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 11/20/1992 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duquesne Light Co, Ohio Edison Co, Pennsylvania Power Co |
| Shared Package | |
| ML20128C847 | List: |
| References | |
| DPR-66-A-167, NPF-73-A-049 NUDOCS 9212040545 | |
| Download: ML20128C843 (27) | |
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UNirED STATES n
I NUCLEAR REGULATORY COMMISSION
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I DUOVESNE LIGHT COMPANY
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OHIO EDISON COMPANY l
r EINNSYLVANIA POWER COMPANY
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DUCKET NO. 50-334 BEAVER VALLEY POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 167 License No. DPR-66 4
1.
The Nuclear Regulatory Commission (the Comission)- has found that:
A.
The application for amendment by Duquesne Light Company, et al.
(the licensee) dated August 24, 1992, complies with the standards and requirements of the Atomic Energy ht s' 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR 2hapter I; B.
1he facility will o)erate in conformity with th'e application, the provisions of t1e Act, and the rules and regulations of.the Comission; 1
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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon-defense and security or to the: health-and ufety of't% puoi c; and S
E.
The issuance of this amendment is in accordance with 10 CFR Part1 51 of the Comission's regulations and all applicable requirements ~
have been satisfied.
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4 9212040545 921120 PDR ADDCK 05000334 I 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 amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendmant No.167, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
t 3.
This license amendment is effective as of the date of its issuance, to to implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jo E F. Stolz, Dir or P ject Directorat. 1-4 ivision of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technlisi Specifications Date of issuance: November 20, 1992 4
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ATTACHMENT T0 l.lCENSE AMENDMENT NO. 167 FACILITY OPERATil(G.!ICENSE N3. DPR-66 DOCKET NO. 50-334 Replace the following pages of Appendix A, Technical Specifications, with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert XXIll XXIII 3/4 7-26 3/4 7-26 3/4 7-27 3/4 7-27 3/4 7-28 3/4 7-28 3/4 7-29 3/4 7-29 3/4 7-30 3/4 7-30 3/4 7-31 3/4 7-31 3/4 7-32 3/4 7-32 P h s 7-6 B 3/4 7-6 C
A l
DPR-66 Table Index (cont.)
l TABLE TITLE PAGE 3.3-11 Accident Monitoring Instrumentation 3/4 3-51 4.3-7 Accident Monitoring Instrumentation 3/4 3-52 Surveillance Requirements 3.3-12 Radioactive Liquid Effluent Monitoring 3/4 3-54 Instrumentation 4.3-12 Radioactive Liquid Effluent Monitoring 3/4 3-57 Instrumentation Surveillance Requirements 3.3-13 Radioactive Gaseous Effluent Monitoring 3/4 3-60 Inttrumentation 4.3-13 Radioactive Gaseous Effluent Monitoring 3/4 3-65 Instrumentation Surveillance Requirements 4.4-1 Minimum Number of Steam Generators to be 3/4 4-10c Inspected During Inservice Inspection 4.4-2 Steam Generator Tube Inspection 3/4 4-10d-4.4-3 Reactor Coolant System Pressure Isolation 3/4 4-14b Valves 3.4-1 Reactor Coolant Syctem Chemistry Limits 3/4 4-16 4.4-10 Reactor Coolant System Chemistry Limits 3/4-4-17 Surveillance Requirements 4.4-12 Primary Coolant Specific Activity Sample 3/4 4-20 and Analysis Program 4.4-5 Reactor Vessel Material Irradiation 3/4 4-26 Surveillance Schedule 3.6-1 Containment Penetrations 3/4 6-19a 3.7-1 Maximum Allowable Power Range Neutron Flux 3/4 7-2 High Setpoint With Inoperable steamline Safety Valves During 3 Loop Operation 3.7-2 Maximum Allowable Power Range Neutron Flux 3/4 7-3 High Setpoint with Inoperable Steamline Safety Valves During 2 Loop Operation 3.7-3 Steamline 5tfety Valves Per Loop 3/4 7-4 4.7-1 Snubbar Visual Iaspection Interval 3/4 7-31
-l 4.7-2 Secondary: Coolant System Specific Activity 3/4 7-9 Sample and Analysis Program BEAVER VALLEY - UNIT 1 XXIII
-Amendment No. 167
e DPR-66 PLANT SYSTEMS 3/4.7.12 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.12 All snubbers shall be OPERABLE. The only snubbers excluded from this requirement are those installed on non safety-related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety-related system.
APPLICABILITY: MODES 1,
2, 3 and 4.
(MODES 5 and 6 for snubbers located on systems / required OPERABLE in those MODES).
ACTION:
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.12.d on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.
SURV LLANCE REQUIREMENTS 4.7.12 Each snubbar shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
i a.
Jnsoection Tvoes As used in this specification, " type of snubber" shall mean l snubbers of the same design and manufacturer, irrespective of capacity.
b.
' Zip _ gal Inspections Snubbers are categorized as inaccessible or accessible during reactor Operation.
Each of these categories (inaccessible and accessible) may be inspected independently according to the l
schedule determined by Table 4.7-1.
The visual inspection interval for each type of snubber shall bo determined based upon l
the critoria provided in Table 4.7-1 and the first inspection interval determined using this criteria shall be based upon the i
previous inspection interval as established by the requirements in effect before amendment 167.
These systems are defined as those portions or subsystems required to prevent releases in excess of 10 CFR 100 limits.
BEAVER VALLEY - UNIT 1 3/4 7-26 Amendment No. 167 i
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4 DPR-66 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) c.
Visual Insnection Accentance Criteria Visual inspections shall verify that:
(3) the inubber has no l visible indications of damage or impaired ovERABILITY, (2) attachments to the foundation or supporting structure are functional, and (3) fasteners for attachment of the snubber to the component and to the snubber anchorage are functional.
Snubbers which appear inoperable as a
result of visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided that:
(1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type that may be generically susceptible; or (2) the affected snubber is functionally tested in the as-found condition and determined OPERABLE por Specification 4.7.12.e or 4.7.12.f, as applicable.
All snubbers found connected to an inoperable common hydraulic fluid reservoir shall be counted as unacceptable for determining the ne t inspection interval.
A review and evaluation shall be performed and documented te iustify continued operation with an continued operation-cannot be unacceptable snubber.
justified, the snubber shall be declarad inoperable and the ACTION requirements shall be met.
Snubbers which have been determined to be inoperable as r result of unexpected transients, isolated damage, or other random events, and cannot be proven operaMe by functional testing for the same reasons, shall not be counted in determining the next visual inspection period when the provision in 4.7.12.d (that failures are subject to an engineering evaluation of component structural integrity) has been met and equipment has been restored to an operable state via repair and/or replacement as necessary.
d.
Functional Testa At least once per 18 months during shutdown, a representative sample (of at least 10 anubbers or at least 10% whichever is less) of the total of each type of snubber in use in the plant-shall be functionaAly tected either in place or in a bench test.
For each enubber cnat does not meet the functional test acceptance criteria of. Specification 4.7.12.e or 4.7.12.f an additional 10 snubbers or at least 10% whichever is less of that type of snubber shall be functional 2y tested.
i BEAVER VALLEY - UNIT 1 3/4 7-27 Amendment No. 167
DPR-66 PLANT SYSTQiS SURVEILLANCE REQUIREMENTS (Continued)
For each large bore snubber (snubbers greater than 1500 kips) on the reactor coolant system that does not meet the functional test acceptance criteria of Specifico?. ion 4.7.12.e, an engineering evaluation is required to determine the failure mode.
If the failure is determined to be generic, an additional 10% (for each f ailure) of that type of snubber shall be functionally tested. If the failure is determined to be non-generic, an additional 10%
(for each failure) of that type of snubber will be torted during the next functional test period.
The representative sample selected for functional testing sha'.1 include the various configurations, operating envirenments and the range of size and capacity of snubbers.
At least 25% of the snubbers in the representative sample shall include snubbers trom the following three categories:
1.
The first snubber away 2 rom each reactor vessel nozzle 2.
Snubbers within 5 feet of heavy equipment (valve, pump, turbine, motor, etc.)
3.
Snubbers within 10 feet of the disenarge from a safety relief valve.
Snubbers that are especially difficult to remove or in high radiation zones during shutdown shall also be included in the representative sample.*
U.a spare snubber has been installed in place of a failed snubber, the spare snubber shall be retested.
Test results of this snubber may not be included for the re-sampling.
If any snubber selected for functional testing either fails to lockup or f ails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all snubbers of the same design subject ?.o the same defect shall be functionally tested.
This testing requirement-shall.be independent of the requirements-stated above for snubbers not meeting the functional test acceptance criteria.
Permancnt or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exemption is presented-and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either. the completion of their fabrication or at a subsequent date.
BEAVER VALLEY UNIT 1 3/4 7-23 Amendment No. 167-
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DPR-66 ELANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
L For the snubber (s) found inoperable, an engineering evaluation shall be performed on the components which arS supported by the snubber (s).
The purpose of this engineering evaluation shall be to determine if the components supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remair.s capable of meeting the designed service.
e.
Hydraulic Snubbers Functional..Teg3 3cceptance Criteria i
The hydraulic snubber functional test shall verify that:
1.
Activation (restraining action) is achieved within the specified range of velocity or acceluration in both tension and compression.
2.
Snubber bleed, or release rate, where required, is within the specified range in compresnion or tension.
For sr.ubbers specifically raquired to not displace under continuous load, the ability of the snubber to withstand lesd without displaccuent shall bo verified.
f.
lipchanical Snybhers Functional Test Acceptancq Criteria The mechanical snubber functional test shall verify that:
1.
The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force.
2.
Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
3.
Snubber releace
- rate, where
- required, is within the specified re.nge in compression or tension.
For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
BEAVER VALLEY - UNIT 1 3/4 7-29 Amendment No. 167
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DPR-66 i
PLANT SYSTEtig SURVE!LLANCE REQUIREMENTS (Continued) m--
g.
Snubhgr, Service I,,1fe MonitotlD9*
The service life of hydraulic and mechanical snutbers shall be conitored to ensure that the service life is not exceeded between surveillance inspections.
The maxir a expected service life for various seals,
- springs, and other critical parts shall be determined and established based on engineering information and may be extended or shortened based on monitored test results end failure history.
Critical parts shall be replaced so that the maximum service life will not be exceeded during a period when the snubber is required to be OPERABLE.
The parts replacements shall be documented and the documentation shall be retained in accordance with Specification 6.10.2.
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5 For purooses of establishing ~a baseline for the deterrination of service life monitoring, this program will be implemented over 3 successive rdueling periods.
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BEAVER VALLEY - UNIT 1 3/4 7-30 Amendment No. 167
DPK-66 TABLZ 4.7-1 ElWDjlER VISUAL INSPECTION INTERVAL NUMBER OF UNACCEPTABLE SNUBBERS Population Column A Column B Column C or Category Extend Interval Repeat Interval Reduce Interval
.Gpigs 1 and 2)
(Notes 3 and 6)
(Notes 4 and 6)
(Notes 5 and 6) 1 0
0 1
80 0
0 2
100 0
1 4
150 0
3 8
200 2
5 13 300 5
12 25 400 8
?,8 36 500 12 24 48 750 20 40 78 1000 or greater 29 56 109 Note 1:
The next visual inspection interval for a type of snubber population or category size shall be determined cased upon the previous inspection interval and the number of unacceptable snubbers found during that interval.
Snubb.'s may be categorized, based upon their accessibility during power operation, as accessible or inaccessible.
These categories may be examined separatel'; or jointly.
- However, the licensee must make and document that decicion before any inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category.
Note 2:
I.nterpolation between population or category sizes and the number of unacceptable snubbers is permissible, bse next lower integer for the value of the limit for Columns A, B, or C if that integer includes a fractional value of unacceptable snubbers as determined by interpolation.
I BEAVF.R VALLEY - UNIT 1 3/4 7-31 Amendment No. 167
DPR-66 TALLE 4.7-1 (CONT'D)
SNUBBER VISUAL INSPECTION INTERVAL Note 3:
If tha number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the previous interval but not greater than 48 months.
Note 4:
If the riumber of unacceptable snubberc is equal to or less than the number in Column B but greater than the number in Column A, the next inspection interval shall be the same as the previous interval.
Note St If the number of unacceptable snubbers is equal to or greater than the number in Column C, the next inspection interval shall be two-thirds of the previous interval.
However, if the number of unacceptable snubbers is less than the number in Column C but greater than the number in Column B,
the ' text interval shall be reduced proportionally by interpolation, that is, the previous interval shall be reduced by a factor that is one-third of the ratio of the dif ference between the number of unacceptable snubbers found during the previous interval and the number in Column B to the differenco in the numbers in Columns B and C.
Note 6:
The provisions of Specification 4.0.2 are applicable for all inspection intervals up to and including 48 months, i
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l BEAVER VALLE)' - UNIT 1 3/4 7-32 Amendment No. 167 (Next Page is 3/4 7-34)
i DPR-66 PLART_lWiiTED BASES 31.1&lLS!MillD1S All saubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related eye <>ms is maintained during and following a seismic or other similar event initiating dynamic loads.
Snul'.be r s excluded from this inspection program are those installed on nonsafety-related systems and then only if their f ailure or f ailure of the system on which they are installed, would have no adverse uffect on any safety-related system.
The visual inspecticn frequency is based upon maintaining a constant level of snubbec protection to each safety-related system during an earthquake or other similar event initiating dynamic loads.
Therefore, the aquired inspection iriterval varies baued upon the number of unacceptable anubbers found during the previous inspection, the total population or category size for each type of snubber, and tne previous inspection interval. This criteria f ollows the guidance provided in NRC Generic Letter 90-09.
Inspections performed before that interval has elapsed may be used ac a new reference point to determine the next inspection. However, the results of such early
)(
inspections performed before the original required time interval has elapsed (r.ominal time less 25%) may not be used to lengthen th3 required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.
When the cause of the rejection of a snubber is clearly establirhed and remedied for that snubber and for any other snubbers that may be generically susceptible, or verified operable by inservice functional
- testing, that snubber may be exempted from being counted as inoperable.
Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly rslated to rejection of the snubber by visual inspection, or are aimilarly located or exposed to thu same environmer.tal conditions such as temperature, radiation and vibration.
When a s'ubber is found inoperable, an engineering evaluation is performed, in addition to the determination of the snubber mode of failure, in order to determine if any-safety-rela wd component or system has been adversely affected by the inoperability of the snubber.
The engineering evaluation shal) determine whether or not the snubber mode of failure nas imparted a significant effect or degradation on the supported component or syntem.
BEAVCR VALLEY - UNIT '
B 3/4 7-6 Amendment No. 167 m
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UNITED STMES i
NUCLEAR REGULATORY COMMISSION E
vf W ASHINGTON, D C. 20!44 S,e...+/
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i DUOVESNE LICHT COMPAtly pHIO EDIS0N COMPANY
]!!E CLEVELAND ELECTRIC IllVMINATING COMPAf(!
THE TOLEDO EDIS0N COMPANY DOCKET NO. 50-412 BEAVER VALLEY POWER STATION. UNIT NO. 2 NiENDMENT TO FACILITY OPERATING LICEN.1E Amendment No. 49 License No. NPF-73 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, et al.
(the licensee) dated August 24, 1992, 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 CF3 Chapter I; P
The facility will operate in conformity with the application, the previsions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurve.e (i) that the activities authorized Sy this amendment can be conducted without endangering tha 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 Cammission's regulations and all applicable requirements have been satisfied.
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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) s.
Facility Operating License No. NPF-73 is hereby amended to read as folicvs:
(2) Technical Specificatigni lho Technical Specifications contained in Appendix A, as revised throL3h Amendment No. 49, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license.
DLCO shall operate the facility in accordance 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 1HE NUCLEAR REGULATORY COMMISSION A
x Jot
- 1. Stolz, Direpto P ject Directorate
-4 t
Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
November 20, 1992 l
i ATTACHMENT TO LICENSE AMENDMENT NO. 49 FAClllTY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 Replace the following pages of the Appendix A Technical-Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert Vil VII 3/4 7-24 3/4 7-24 3/4 7-25 3/4 7-25 3/4 7-27 3/4 7-27 3/4 7-28 3/4 7-28 3/4 7-29 3/4 7-29 3/4 7-30 3/4 7-30 8 3/4 7-5 B 3/4 7-5 B 3/4 7-6 8 3/4 7-6 4
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NPF-73 INDEX j
I LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS t
SECTION P.Mi3 containment Recirculation Spray System 3/4 6-12 Chemical Addition System 3/4 6-14 3/4.6.3 CONTAINMENT ISOLATION VALVES 3/4 6-15 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Analyzers 3/4 6-31 Electric Hydrogen Recombiners.
3/4 6-32 3/4.6.5 SUBATMOSPHERIC PRESSURE CONTROL SYSTEM Steam Jet Air Ejector.
3/4 6-34 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Valves.
3/4 7-1 Auxiliary Feedwater System 3/4 7-4 Primary Plant Domineralized Water (PPDW) 3/4 7-6 Activity 3/4 7-7 Main Steam Line Isolation Valves 3/4 7-9 3/4.7.2 STEAM CENERATOR PRESSURE / TEMPERATURE LIMITATION.
3/4 7-10 3/4.7.3 PRIMARY COMPONENT COOLING MATER SYSTEM.
3/4 7._.....
3/4.7.4 SERVICE WATER SYSTEM (SWS) 3/4 7-12 3/4.7.5 ULTIMATE HEAT SINK - OHIO-RIVER.
3/4 7-13--
3/4.7.6 FLOOD PROTECTION 3/4.7-14 3/4.7.7 CONTROL ROOM EMERGENCY HABITABILITY SYSTEMS 3/4 7-15 3/4.7.8 SUPPLEMENTAL LEAK COLLECTION AND-RELEASE SYSTEM SLCRS) 3/4 7-18 3/4.7.9 SEALED SOURCE CONTAMINATION.
3/4_7-20 3/4.7.12 SNUBBERS 3/4 7-24 3/4 7-30 l-3/4.7.13 STANDBY SERVICE WATER SYSTEM (SWE) 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1-A.C.
SOURCES Operating.
3/4 8..-...............
4 3/4 8-6 Shutdown t
. BEAVER VALLEY - UNIT 2 VII Amendment No. 49
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c
INDEX LIMITING _ CONDITION FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION PAGE 3/4.8.2 ONSITE POWER DISTDIBUTION SYSTEMS A.C. Distribution - Operating..............................
3/4 8-7 A.C. Distribution -
Shutdown...............................
3/4 8-8 D.C. Distribution -
Operating..............................
3/4 8-9 0.C. Distribution -
Shutdown...............................
3/4 8-12 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION........................................
3/4 9-1 3/4.9.2 INSTRUMENTATION............................................
3/4 9-2 3/4.9.3 D E C AY 1 1 M E.................................................
3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS..........................
3/4 9-4 3/4.9 S COMMUNICATIONS.............................................
3/4 9-S 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 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION..............
3/4 9-8 3/4.9.9 CONTAINMENT PL'RGE AND EXHAUST ISOLATION SYSTEM.............
3/4 9-10 3/4.9.10 WATER LEVE L-REACTOR VESSEL.................................
3/4 9-11 3/4.9.11 STORAGE POOL WATER LEYEL..................................
3/4 9-12 3/4.9.12 FUEL BUILDING VENTILATION SYSTEM - FUEL M0VEMENT.................................................
3/4 9-13 3/4.9.13 FUEL BUILDING VENTILATION SYSTEM - FUEL ST0 RAGE..................................................
3/4 9-14 l
3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN......................................,
3/4 10-1 1
3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS.....
3/4 10-2 i
3/4.10.3 PHYSICS TESTS.............................................
3/4 10-3 l
3/4.10.4 REACTOR COO LANT L00 PS.....................................
3/4 10-4 3/4.10.5 POSITION INDICATION SYSTEM-SHUTDOWN.......................
3/4 10-5 l
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BEAVER VALLEY - UNIT 2 VIII
PLANT SYSTEMS 3/4.7.11 (This specification number is not used) t 0
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BEAVER VALLEY - UNIT 2 3/4 7-23.
l NPF-73 PLANT SYSTDiS 3/4.7.12 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.12 All snubbers shall be OPERABLE.
The only snubbers excluded from this requirement are thbae installed on non-safety-related systems and then only if their failure or failure of the system on which they are installed, would have no advs.rse effect on any safety-related system.
APPLICABILIIX:
MODES 1, 2,
3 and 4.
(MODES 5 and 6 for snubbers located on systems
- required OPERABLE in those MODES).
ACTION:
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.12.d on the supported l component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.12 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
a.
Inspection Tvoes As used in this specification,
" type of snubber" shall mean snubbers of the same design and manufacturer, irrespective of capacity.
b.
Visual Inscections Snubbers are categorized as inaccessible or accessible during reactor operation.
Each of these categories (inaccessible and accessible) may be inspected independently
, cording to the schedule determined by Table 4.7-1.
The visual inspection interval for each type of snubber shall be determined based upon L
the criteria provided in Table 4.7-1 and the first inspection interval determined using this criteria shall be based upon the previous inspection interval as establis'ed by the requirements in effect before amendment 49.
These systels are defined as those portions or subsystems required to prevent releases in excess of 10 CFR 100 limits.
f BEAVER VALLEY - UNIT 2 3/4 7-24 Amendment No. 49
NPF-73 EZJJT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) c.
yh ual Insoection Accentance criteria visual inspections shall verify thatt (1) the snubbor has no visible indicatior.s of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are functional, and (3) fasteners for attachment of the snubber to the component and to the snubber anchorage are functional.
Snubbers which appear inoperable as a result of the visual inspections shall be classified as unacceptable an6 may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided thatt (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type that may be generically susceptible; or (2) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per Specification 4.7.12.e or 4.7.12.f. as applicable.
All snubbers found connected to an inoperable common hydraulic fluid reservoir shall be counted as unacceptable for determining the next inspection interval.
A review and evaluation shall be performed and documented to justify continued operation with an unacceptable snubber.
If continued operation cannot be justified, the snubber shall be declared inoperable and the ACTION requirements shall be met.
Snubbers which have been determined to be inoperable as a result of unexpected transients, isolated damage, or other random (vents, and cannot be proven operable by functional testing for the same reasons, shall not be counted in determining the next visual inspection period when the provision in 4.7.12.d (that l failures are subject to an engineering evaluation of component structural integrity) has been met and equipment has been restored to an operable state via repair and/or replacement as necessary.
d.
Functional Tests l
At least once per 10 months during shutdown, a representative sample (of at least 10%) of the total of each type of snubber in use in the plant shall be functionally testod either in place or in a bench test.
For Functional Testing type of snubber shall mean a group or combination of groups by load size and kind (i.e., hydraulic or mechanical) or any other combination of load size and kind.
For sach snubber that does not meet the functional test acceptance criteria of Specification 4.7.12.0 or j
4.7.12.f, an additional 10% shall be functionally tested.
1 BEAVER VALLEY - UN D 2 3/4 7-25 Amendment No. 49 l
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
Tne representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers.
At least 25% of the snubbers in the representative sample shall include snubbers from the following three categories:
1.
The first snubber away from each reactor vessel nozzle.
2.
Snubbers within 5 feet of heavy equipment (valve, pump, turbine, motor, etc.).
3.
Snubbers within 10 fer' af the discharge from a safety relief valve.
Snubbers that a n especially difficult to remove or in high radiation zones during shutt'own shall also be included in the representative sample.*
If a spare snubber has been installed in place of a failed snubber, the spare snubber shall be retested. -Test results of this snubber may not be included for the re-sampling.
If any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer cr design deficiency all si.ubbers of the same design subject to the same defect shall be functionally tested.
This testing requirement shall be inGependent of the require-ments stated above for snubbers not meeting the functional test acceptance criteria.
For the snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snubber (s).
The purpose of this engineering evaluation shall be to determine if the components supported by the snubber (s) were adversely affected by the inoperability of the sn@ber(s) in order to ensure that the supported component remains capable of meeting the designed service.
- Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.
I 1
BEAVER VALLEY - UNIT 2 3/4 7-26
MPF-73 Es.HT EYS71E SURVEILLANCE REQUIREMENTS (Continued)
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livdr6ulic Snubbers Functional _ Test Accent 4' f,riteri,;
The hydraulic snubber functional test shalt. '9rify that:
Ac.*:.ivation (restraining action) is achieved '-tithin the
- ified range of velocity or acceleration in both tension comprecsion.
?.
abber bleed, or release rate, where required, is_within
.au spr ified range in compression or tension.
For snubbers voocifically required to not displace under continuous load, Dility of the snubber to withstand load 1.ithout m
apla r.:ement shall be verified.
e f.
aechanical Snv&bers Functioral Test AccootApce Criteria The mechanical snubber functional test shall verify that:
1.
The force that initiates f ree movement o." the snubber rod in either tension or compression is less.. M.: the specified l
maximum drag force.
3 4
2.
Act.ivation
' restraining action As cr..iw ed within the speciff a m of velocity or acceleracion in both tension
< sd comp,
slen.
3.
3nubber release r e.t e,
where
- requited, is within the
<spacifie/ range in compression or tension.
For snubbers g
specifically recuired not to displace under continuous load, g
s the ability of the snubber to withstand load wit %ut displacement shall be verifieL g.
Service Life Monitorino l
The service life of hydraelic and mechanical snubbers shall be monitored to ensure that the service life is not exct-ded between su: veillance inspections.
The maximum expected service l'.fe for various seals,
- springs, and other critical parts sh 9til be determined and established based on engineering information a.d may be extended or sh rtened based on monitored test results and failure history.
Critical parts shall be replaced so that the maximum nervice life will r.st be exceeded during a period when the onobber is recruired to be OPERABLE.
The parts replacements shall be documented and the documentation shall be retained in accordance wi th Specification 6.10.2.
Service. life will be defined to commence at plant startup subsequent to initial fuel load.
BEAVER VALLEY - UNIT 2 3/4 7-27 Amendment t.-
49 e
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NPT-73 TABLE 4.7-1 SNUBBER VISUAL INSPECTION INTERVAL NUMBER OF UNACCEPTABLE SNUBBERS Population Column A Column B Column C or Category Extend Interval Repeat Interval Reduce Interval j
(Notes 1 and 2)
(Notes 3 and 6)
(Notes 4 and 6)
(Notes _5 and 6) 1 0
0 1
80 0
0 2
100 0
1 4
150 0
3 8
200 2
5 13 300 5
12 25 400 8
18 36 500 12 24 48 750 20 40 78 1000 or greater 29 56 109 Note 1:
The naxt visual inspection interval-for a type of snubier population or category size shall be determined bat;sd upon the previous inspection interval and the number of unacceptable snubbers found during that interval.
Snubbers may be categorized, based upon their accessibility during power operation, as arcessible or inaccecsible.
These categories nay be examined separately or jointly.
- However, the licensee must make and dccument that decision before any inspection _ar4 shall use that decision as the basis upon
';inich to determine the next inspection interval for that category.
Note 2:
Interpolation between popt: ation or category sizes and the number of unacceptable snuobers is permissible.
Use next lower integer fer the value of the limit for Columns A, B,
or C if that integer includes a fractional value 'of unacceptable snubbers as determined by interpolation.
BEAVER VALLEY - UNIT 2
?v4 7-28 Amendment No. 49 u
NPF*73 TA7LE 4.7-1 (CONT'D) l SNUBBER VISUAL INSPECTION INTERyAL Note 3:
If the number cf unacceptabla sr.ubbers is equal to or less than the number in Column A, the next inspection interval may be twice the previous interval but not greater than 48 monthu.
Note 4:
If the number or unacceptable snubbers is equal to or less than the number in Column B but greater than the number in Column A. the next inspection interval s 11 be the same as the previous interval.
Note 5:
If the number of unacceptable snubbers is equal to or groater than the number in Column C, the next inspection interval shall be two-thirds of the previous interval.
However, if the number of unacceptable snubbers is less than the number in Column C but greater than the number in Column B,
the next interval shall be reduced proportionally by interpolation, that is, the previous interval shall be reduced by a factor that is one-third of the ratio of the dif ference between the number of unacceptable snubbers found during the previous interval and th6 number in Column B to the difference in the numbers in Colun.ns B and C.
Note 6:
Tne provisions of Specification 4.0.2 are applicable for all inspection intervals up to and including 48 months.
. BEAVER VALLEY - UNIT 2 3/4 7 29 Amendment No. 49 t.
NPF-73 PLANT SYSTEMS 3/4.7.13 STANDBY SERVICE WATER SYSTEM (SWE)
LIMITING CONDITION FOR OPERATION 3.7.13.1 At least one standby service water subsystem shal' be OPERABLE.
APPLICABILITY:
MODES 1, 2,
3, and 4.
ACTION:
With less than one SWE subsystem OPERABLE, restore at lee-t one subsystem to OPERABLE status within 7 days or be in at le".at 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 hours.
SURVEILLANCE REQUIREMENTS r
4.7.13.1 At least one SWE subsystem shall be demonstrated OPERABLE:
a.
At least once per 92 days, by verifying that each pump develops at least 109 paid differential pressure, while puxaping through its test flow line.
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 Service 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 />.
BEAVER VALLEY - UNIT 2 3/4 7-30 Amendment No. 49
NPF-73 3/4.7 PLANT SYSTEMS BASES 3/4.7.9 SEALED SOURCE CQNTAMINATION The limitations on sealed source ce'itamination ensure that the total body or individual organ irradiation does not exceed allowable limits in the event of ingestion or inhalation of the source material. The limitatiors on removable contamination for sources requiring leak testing, including alpha emitters, 10 based on 10 CFR 70.39(c) limits for plutonium.
Leakage of sources excluded from the requirements of this specification represent less than one maximum permissibic body burden for total body irradiation if the source material is inhaled or ingested.
Scaled sources ate classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group.
Those sources which are frequently handled are required to be tested more often than those which are not. Scaled sources which are continuously enclosed within a shielded mechanism (i.e.,
sealed sources sithin radiation monitoring or boron measuring devices) cre considered to be stored and need not be tested unless they are removed from the shielded mechanism.
J/4.7.10 and 3/.i.7.11 RESIDUAL HEAT RE}iQVAL SYSTEM (RHR1 Deleter!
U4.7,12 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other similar event initiating dynamic loads.
Snubbers-excluded from this inspection program are those installed on :,onsafety-related systems I
and then only if their failure or f ailure of the sy, tem on which they l
ara installed, would hive no adverse effect on any safety-related I
- system, i
The visuti inspection frequency is based upon maintaining a constant level of snubber prots.ction to systems.
Therefore, the required inspection interval varies based upon the number of l.
unacceptable snubbers found during the previous inspection, the total population or category size for each type of snt bber, and the previous inspection interval.
This criteria follows the quidance provided in NRC Generic Letter 90-09.
Inspections parformed before that laterval has elapased may be used as a new reference point to determine the next inspection.
When the cause of the rejection of a snubber is clearly established and remedied for that enubber and for any other snubbers that may be generically susceptible, or verified OPERABLE by BEAVER VALLEY - UNIT 2 B 3/4 7-5 Amendment No. 49 o
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HPF-73 PLANT SYSTEM _S BASES ENUBBERS (Continued) inservice functional testing, that snubber may be exempted from being counted as inoperable.
Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection cf the snubber by visual inspection, or are similarly located or expcsed to the same environmental conditions such as temperature, radiation and vibration.
When a snubber is found inoperable, an engineering evaluation is parformed, in addition to the determination of the snubber mode of failure, in order to determine if any safety-related component;or system has been adversely affected by the inoperability of the snubber.
The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.
To provide asourance of rnubber functional reliability, a
representative sample of the installed snubbers will be functionally tested during plant shutdowns at refueling or 18 month intervals nct to exceed two (2) years.
Observed fal]ures of these sample snubbera shall require functional testing of additional units.
Snubbers are classified and grouped by design and manufacturer but not by size.
For example, mechanical snubbers utilizing the same design features of the 2-kip, 10-kip and 100-kip capreity manufactured by Company "A"
are of the same type.
Thc same design L.echanical snubbers manufactured by Company "C" for the purposes of this Technical Specification would be of a different type, as would hydraulic snubbers from either manufacturer, she service life of a snubber is evaluated via menufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc... ).
The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions.
These records will provide statistical bases for future consideration of snubber service life.
The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.
3/4.7.13 STANDBY SERVICE WATER SYSTEM (SWEL The OPERABILITY of the SWE ensures that sufficient cooling capacity is available to bring the reactor to a cold shutdown condition in the event that a barge explosion at the station'.u intake structure or any other extremely remote event would render all of the normal Service Water System supply pumps inoperable.
BEAVER VALLEY - UNIT 2 B 3/4 7-6 Amendment No. 49 1