ML20137S823
| ML20137S823 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 09/24/1985 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20137S830 | List: |
| References | |
| GL-84-13, TAC-57295, TAC-57296, TAC-59278, TAC-59279, NUDOCS 8509300515 | |
| Download: ML20137S823 (38) | |
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U~NTI ED STATES
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20S55 e
SOUTHERN CALIFORNIA ED! SON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-361 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 33 License No. NPF-10 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the license for San Onofre Nuclear Generating Station, Unit 2 (the facility) filed by the Southern California Edison Company on behalf of itself and San Diego Gas and Electric Company, The City of Riverside and the City of Anaheim, California (licensees), dated January 23, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the 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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license anendment will not be inimical to the comon defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 nf the Comission's regulations and all applicable requirements have been satisfied.
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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. NPF-10 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 33, are hereby incorporated in the license.
SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective immediately and is to be fully implemented i
within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION j
/t i
George. Knighton ief Licensing Branch No. 3 r
Division of Licensing i
Attachment:
Changes to the Technical i
Specifications Date of Issuance: September 24, 1985 1
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September 24, 1985
...- l ATTACHMENT TO LICENSE AMENDMENT N0_.__33, FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 d
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. Also to be replaced are the following overleaf pages to the amended pages.
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Amendment Pages Overleaf Pages i
XXI XXII l
3/4 7-16 3/4 7-15 3/4 7-17 I
3/4 7-18 3/4 7-19 3/4 7-20 3/4 7-21 3/4 7-22 3/4 7-23 3/4 7-24 4
8 3/4 7-5 B 3/4 7-6 6-23 6-24
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1
- - - - -- -. ~.'
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INDEX LIST OF TABLES l:
TABLE PAGE t
j 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM..............................
3/4 7-8 I
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3.7-5 SAFETY-RELATED. SPRAY AND/0R SPRINKLER SYSTEMS............
3/4 7-31 3.7-6 FIRE HOSE STATIONS.......................................
3/4 7-33 4.8-1 DIESEL GENERATOR TEST SCHEDULE...........................
3/4 8-7 l
1 4.8-2 BATTERY SURVEILLANCE REQUIREMENTS........................
3/4 8-11 i
3.8-1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT 1
i PROTECTIVE 0EVICES.......................................
3/4 8-18 3.8-2 MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION BYPASS DEVICES...........................................
3/4 8-32 j
3.10-1 RADIATION MONITORING / SAMPLING EXCEPTIONS.................
3/4 10-6 I
4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM...
3/4 11-2
'I 4.11-2 RADI0 ACTIVE GASECUS WASTE SAMPLING AND ANALYSIS j
PR0 GRAM..................................................
3/4 11-9 f
3.12-3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM............
3/4 12-3 i
3.12-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES....................................
3/4 12-7 f
4.12-1 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECION (LLD)....
3/4 12-8 i
B 3/4.4-1 REACTOR VESSEL T0VGHNESS.................................
B 3/4 4-8 I
j 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS.....................
5-8 6.2-1 MINIMUM SHIFT CREW COMPOSITION...........................
6-4 I
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l SAN ONOFRE-UNIT 2 XXI AMENDMENT NO. 33
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INDEX i
LIST OF FIGURES FIGURES PAGE 3.1-1 MINIMUM BORIC ACID STORAGE TANK VOLUME AND TEMPERATURES AS A FUNCTION OF STORED BORIC ACIO CONCENTRATION.........
3/4 1-13 i
i 3.1-2 CEA INSERTION LIMITS.....................................
3/4 1-24 l
3.2-1 DN8R MARGIN OPERATING LIMIT BASED ON C0LSS...............
3/4 2-7 3.2-2 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE).......................
3/4 2-8 3.3-1 DEGRADED BUS VOLTAGE TRIP SETTING........................
3/4 3-40 4.4-1 TUBE WALL THINNING ACCEPTANCE CRITERIA...................
3/4 4-15a 3.4-1 DOSE EQUIVALENT I-131 PRIMARY COOLANT SPECIFIC ACTIVITY LIMIT...........................................
3/4 4-26 3.4-2 HEATUP RCS PRESSURE / TEMPERATURE LIMITATIONS i
FOR 0-5 YEARS............................................
3/4 4-29 3.4-3 COOLDOWN RCS PRESSURE / TEMPERATURE LIMITATIONS FOR 0-5 YEARS................................................
3/4 4-30 3.7-1 MINIMUM REQUIRED FEE 0 WATER INVENTORY FOR TANK T-121 FOR MAXIMUM POWER ACHIEVED TO DATE............
3/4 7-6A 5.1-1 EXCLUSION AREA...........................................
5-2 l
5.1-2 LOW POPULATION Z0NE......................................
5-3 j
5.1-3 SITE BOUNDARY FOR GASEOUS EFFLUENTS......................
5-4 5.1-4 SITE BOUNDARY FOR LIQUID EFFLUENTS.......................
5-5 j
6.2-1 0FFSITE ORGANIZATION.....................................
6-2 l
6.2-2 UNIT ORGANIZATION........................................
6-3 i
j 6.2-3 CONTROL ROOM AREA........................................
6-4a i
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i SAN ONOFRE-UNIT 2 XXII AMENOMENT NO. 33 i
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1 PLANT SYSTEMS 4
i SURVEILLANCE REQUIREMENTS (Continued) f.
After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99.95% of the 00P when they are tested in place in accordance with i
ANSI N510-1975 while operating the system at a flow rate of 2050
- 150 cfm for the ventilation unit and 35,485 cfm i 10% for the air conditioning unit.
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After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99.95% of a halogenated hydrocarbon refrigerant test gas I
when they are tested ! replace in accordance with Ai4SI N510-1975 I
while operating the system at a flow rate of 2050
- 150 cfm for the ventilation unit and 35,485 cfm i 10% for the air conditioning unit.
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SAN ONOFRE-UNIT 2 3/4 7-15
PLANT SYSTEMS 3/4.7.6 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.6 All snubbers-shall be OPERABLE.
The caly snuobers excluded from this requirement are those installed on nonsafety-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 4.7.6.g on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.6 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program, a.
Inspection Types As used in this specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity.
b.
Visual Inspections The first inservice visual inspection of snubbers shall be performed af ter 4 months but within 10 months of commencing POWER OPERATION and shall include all snubbers. If less than two snubbers are found inop-erable during the first inservice visual inspection, the second in-service visual inspection shall be performed 12 months i 25% from the date of the first inspection.
Otherwise, subsequent visual inspec-tions shall be performed in accordance with the following schedule:
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SAN ONOFRE-UNIT 2 3/4 7-16 AMENDMENT NO. 33
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) l No. Inoperable Snubbers Subsequent Visual,
per Inspection Period Inspection Period
- 0 18 months i 25%
1 12 months t 25%
2 6 months i 25%
3,4 124 days i 25%
5,6,7 62 days i 25%
8 or more 31 days i 25%
The snubbers may be categorized into two groups:
Those accessible and those inaccessible during reactor operation.
Each group may be inspected independently in accordance with the above schedule.
c.
Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indi-cations of damage or impaired OPERABILITY and (2) attachments to the foundation or supporting structure are secure.
Snubbers which appear' inoperable as a result of visual inspections may be determined OPERABLE 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 that may be generically susceptible; and (2) the affected snubber is functionally tested in the as found condition and deter-mined OPERABLE per Specification 4.7.6.e or 4.7.6.f, as applicable.
However, when a fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined inoperable and cannot be determined OPERABLE via functional testing for the purpose of estab-lishing the next visual inspection interval.
All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.
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The inspection interval shall not be lengthened more than one step at a time.
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- The provisions of Specification 4.0.2 are not applicable.
SAN ONOFRE-UNIT 2 3/4 7-17 AMENOMENT NO. 33
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.
Functional Tests At least once per 18 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 tested either in place or in a bench test.
For each snubber of a type that does not meet the functional test acceptance criteria of Specification 4.7.6.e or 4.7.6.f, an additional i
10% of that type of snubber shall be functionally tested until no more failures are found or until all snubbers of that type have been functionally tested.
The 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 with'in 5 feet of heavy equipment (valve, pump, turbine motcr,etc.)
3.
Snubbers within 10 feet of the discharge 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.*
In addition to the regular sample, snubbers which failed the' previous functional test shall be retested during the next test period.
If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested.
Test results of those snubbers may not be included for the re-sampling.
- Permanent or other exemptions from functional testing for individual snubbers in these caterories may be granted by the Commission only if 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.
SAN Ot10FRE-UNIT 2 3/4 7-18 AMEN 0 MENT fi0. 33 i
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4 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) i e.
Hydraulic Snubbers Functional Test Acceptance Criteria
- 1 The hydraulic snubber functional test shall verify that:
Activation (restraining action) is achieved within the 1.
specified range of velocity or acceleration in both tension and compression.
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2.
Snubber bleed or release rate, where required, is within the specified range in compression or tension.
For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
f.
Mechanical Snubbers Functional Test Acceptance Criteria
- The mechanical snubber functional test shall verify that:
1.
The force required to initiate or maintain motion of the snubber is within the specified range in both direct.ons of travel.
2.
Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
3.
Snubber release rate, where required, is within the specified range 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.
j g.
Functional Test Failure Analysis An engineering evaluat4n shall be made of each failure to meet the functional test acceptance crl+?ria to determine the cause of the failure.
The results of this evaluation shall be used, if applicable, in selecting snubbers to be tested in an effort to determine the l
OPERABILITY of other snubbers irrespective of type which may be l
subject to the same failure mode.
j For the snubbers found inoperable, an engineering evaluation shall be performed on the components to which the inoperable snubber are attached.
The purpose of this engineering evaluation shall be to
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determine if the components to which the inoperable snubbers were j
attached were adversely affected by the inoperability of the snubbers i
in order to ensure that the component remains capable of meeting the i
designed service.
- Testing methods may be used to measure parameters indirectly or parameters other than those specified if those results can be correlated to the i
specified parameters through established methods.
i SAN ONOFRE-UNIT 2 3/4 7-19 AMEN 0 MENT NO. 33 I
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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
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 or design deficiency all snubbers' of the same type subject to the same defect shall be functionally tested.
This testing requirement shall be independent of the requirements stated in Specification 4.7.6.e. or 4.7.6. f. for snubbers not meeting the functional test acceptance criteria.
h.
Functional Testing of Repaired and Replaced Snubbers Snubbers which fail the visual inspection or the functional test acceptance criteria shall be repaired or replaced.
Replacement snubbers and snubbers which have repairs which might affect the functional test resu.It shall be tested to meet the functional test criteria before instillation in the unit.
These snubbers shall have met the acceptace criteria subsequent to their most recent service, and the functional test must have been performed within 12 month before being installed in the unit.
i.
Snubber Service Life Monitoring A record of the service life of each snubber, the date at which the designated service life commences and the instal-lation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.1.
Concurrent with the first inservice visual inspection and at least once per 18 months thereafter, the installation and maintenance records for each snubber shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review.
If the indicated service life will be exceeded prior to the next scheduled snubber service life revies, the snubber service life shall be reevaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled servica life review.
This reevaluation, replacement or reconditioning shall be indicated in the records.
J.
Refueling Outage Inspections During each refueling outage an inspection shall be performed of snubbers attached to sections of safety systems piping that have experienced unexpected, potentially damaging transients as determined from a review of operational data and a visual inspection of the systems.
In addition to satisfying the visual inspection acceptance criteria, freedom of motion of mechanical snubbers shall be verified using one of the following:
(i) manually induced snubber movement; (ii) evaluation of in place snubber piston setting; (iii) stroking the mechanical snuhber through its full range of travel.
i SAN ONOFRE-UNIT 2 3/4 7-20 AMENDMENT NO. 33
e 4
4 THIS PAGE INTENTIONALLY LEFT BLANK SAN ONOFRE-UNIT 2 3/4 7-21 At1ENDf4ENT NO. 33
THIS PAGE INTENTIONALLY LEFT BLANK SAtt Ot10FRE-UtlIT 2 3/4 7-22 AMEN 0 MENT NO. 33
THIS PAGE INTENTIONALLY LEFT BLANK SAN ONOFRE-UNIT 2 3/4 7-23 AMENDMENT NO. 33
PLANT SYSTEMS 3/4.7.7 SEALED SOURCE CONTAMINATION t
LIMITING CONDITION FOR OPERATION i
i 3.7.7 Each sealed source containing radioactive material either in excess of
'100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 microcuries of removable contamination.
APPLICABILITY: At all times.
j ACTION:
a.
With a sealed source having removable contamination in excess of the i
above limit, withdraw the sealed source from use and either:
1.
Decontaminate and repair the sealed source, or 2.
Dispose of the sealed source in accordance with Commission j
Regulations.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
i SURVEILLANCE REQUIREMENTS I
4.7.7.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:
a.
The licensee, or I
b.
Other persons specifically authorized by the Commission or an Agreement State.
2 The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.
4.7.7.2 Test Frequencies - Each category of sealed sources (excluding startup source = and fission detectors previously subjected to core flux) shall be tested at the frequencies described below.
i a.
Sources in use - At least once per six months for all sealed sources containing radioactive material:
1.-
With a half-life greater than 30 days (excluding Hydrogen 3),
i and 2.
In any form other than gas.
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SAN ONOFRE-UNIT 2 3/4 7-24
PLANT SYSTEMS BASES i
3/4.7.6 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 event initiating dynamic loads.
Snubbers excluded from this inspection program are those installed on nonsafety 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.
For visual inspection snubbers are categorized into two (2) groups, those accessible and those inaccessible during reactor operation.
For functional testing, snubbers are categorized into types by design and manufacturer, irre-spective of capacity.
For example, Pacific Scientific snubbers are divided into four types corresponding to different design features:
PSA 1/4 and 1/2 are one type; PSA 1, 3, and 10 are another; PSA 6 is another; and PSA 35 and 100 are a fourth type.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection.
Inspections performed before that interval has elapsed may be used as a new reference point to deter-i mine the next inspection.
However, the results of such early inspections per-4 formed before the original required time interval has elapsed (nominal time less 25%) may rot be used to lengthen the required inspection interval.
Any j
inspection whose results require a shorter inspection interval will override j
the previous schedule.
1 To provide assurance of snubber functional reliability, a representative i
sample of the installed snubbers will be functiona,lly tested during plant shut-downs at 18 month intervals.
Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance programs.
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SAN ONOFRE-UNIT 2 B 3/4 7-5 AMEN 0 MENT NO. 33
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PLANT SYSTEMS BASES SNUBBERS (Continued)
The service life of a snubber is evaluated via manufacturer 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.
3/4.7.7 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.
Sealed sources are 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.
Sealed sources which are continuously enclosed wi~ thin a shielded mechanism (i.e. sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shield mechanism.
3/4.7.8 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located.
The fire suppression system consists of the water system, spray and/or sprinklers, and fire hose stations.
The collective capability of the fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program.
In the event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service. When the inoperable fire fighting equipment is intended for use as a backup means of fire suppression, a longer period of time is allowed to provide an alternate means of fire fighting than if the inoperable equipment is the primary means of fire suppression.
The surveillance requirements provide assurance that the minimum OPERABILITY requirements of the fire suppression systems are met.
SAN ONOFRE-UNIT 2 B 3/4 7-6
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ADMINISTRATIVE CONTROLS I
I h.
Records of in-service inspections performed pursuant to these Technical Specifications.
i.
Records of Quality Assurance activities required by the QA Manual.
j.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k.
Records of meetings of the OSRC and the NSG.
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b l
1.
Records of the service lives of all snubbers within the scope of f
Technical Specification 3/4.7.6 including the date at which the j
service life commences and associated installation and maintenance records.
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Records of secondary water sampling ano water quality.
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6.11 RADIATION PROTECTION PROGRAM l
l Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and j
adhered to for all operations involving personnel radiation exposure.
4 6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and-entrance thereto shall be controlled by requiring issuance of a Radiation Exposure Permit (REP)*. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
A radiation monitoring device which continuously indicates the a.
radiation dose rate in the area, b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made after the~ dose rate level in the area has.been established and personnel have been made knowledgeable of them.
- Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the REP issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise following approved plant radiation protection procedures for entry into high radiation areas.
l SAN ONOFRE-UNIT 2 6-23 AMENDMENT NO. 33
i ADMINISTRATIVE CONTROLS c.
An individual qualified in radiation protection procedures who is i
equipped with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation Exposure Permit.
6.12.2 In addition to the requirements of 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour.a dose greater than 1000 mrem shall.be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the. Shift Supervisor on duty and/or health physics supervision.
Doors shall remain locxed except during periods of access by personnel under an j
approved REP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that ' area.
For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose in excess of 1000 mrem"* that are located within large areas, such as. PWR containment, where 1
no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device.
In lieu of the stay time specification of the REP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.
6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.#
6.13.2 Licensee initiated changes to the PCP:
1.
Shall be submitted to the Commission in the semi-annual Radioactive Effluent Release Report for the period in which the change (s) was l
made.
This submittal shall contain:
Sufficiently detailed information to totally support the rationale a.
for the change without benefit of additional _ or, supplemental information; b.
A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and c.
Documentation of the fact that the change has been reviewed and found acceptable pursuant to 6.5.2.
2.
Shall become ' effective upon review and acceptance pursuant to 6.5.2.
^^ Measurement made at 18" from source of radioactivity.
- The PCP shall be submitted and approved prior to shipment of " wet" solid
= radioactive waste.
SAN Ot40FRE-UNIT 2 6-24 AMEN 0 MENT NO. 25 m-,w,
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%)
....+
SOUTHERN CALIFORNIA EDIS0N COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET N0. 50-362 SAN ON0FRE NUCLEAR GENERATING STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 22 License No. NPF-15 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the license for San Onofre Nuclear Generating Station, Unit 3 (the facility) filed by the Southern California Edison Company on behalf of itself and San Diego Gas and 7
. Electric Company, The City of Riverside and the City of Anaheim, California (licensees), dated January 23, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as 1
amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission; 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 set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable reouirements have been satisfied.
=
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-15 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 22, are hereby incorporated in the license.
SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective immediately and is to be fully implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
,A' George
- Knighton, Licensing Branch No. 3 e
Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 24, 1985
.. -. _. - - ~.
September 26, 1985
. ATTACHMENT TO LICENSE. AMENDMENT N0. 22 FACILITY OPERATING LICENSE NO. NPF-15 DOCKET N0. 50-362 j
Replace the following pages of the Appendix A Technical Specifications with
- i the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Also to be replaced are the following overleaf pages to the amended pages.
Amendment Pages Overleaf Pages XVII XVIII l
XX XIX i
3/4 7-17 t
3/4 7-18 3/4 7-19 1
3/4 7-20 3/4 7-21 3/4 7-22 3/4 7-23 3/4 7-24 B3/4 7-5 B3/4 7-6 6-24 6-23 i
'l 1
i i
b a
n_,,,_.,,.,___.v,,w.
,,,s,
INDEX LIST OF FIGURES FIGURE PAGE 3.1-1 MINIMUM BORIC ACIO STORAGE TANK VOLUME AND TEMPERATURE AS A FUNCTION OF STORED BORIC ACID CONCENTRATION........
3/4 1-13 3.1-2 CEA INSERTION LIMITS VS FRACTION OF ALLOWABLE THERMAL P0WER...................................................
3/4 1-24 3.2-1 DNBR MARGIN OPERATING LIMIT BASED ON C0LSS..............
3/4 2-7 3.2-2 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE)......................
3/4 2-8 3.3-1 DEGRADED BUS VOLTAGE TRIP SETTING.......................
3/4 3-40 4.4-1 TUBE WALL THINNING ACCEPTANCE CRITERIA..................
3/4 4-16 3.4-1 DOSE EQUIVALENT I-131 PRIMARY COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE PRIMARY COOLANT SPECIFIC ACTIVITY >1.0 pCi/ GRAM DOSE EQUIVALENT I-131........................................
3/4 4-27 3.4-2 NEATUP RCS PRESSURE / TEMPERATURE LIMITATIONS FOR 0-5 YEARS...............................................
3/4 4-30 3.4-3 C00LDOWN RCS PRESSURE / TEMPERATURE LIMITATIONS FOR 0-5 YEARS...............................................
3/4 4-31 3.7-1 MINIMUM REQUIRED FEEDWATER INVENTORY FOR TANK T-121 FOR MAXIMUM POWER ACHIEVED TO 0 ATE..........................
3/4 7-7 l
5.1-1 EXCLUSION AREA......................;...................
5-2 5.1-2 LOW PO PU LATIO N Z0 N E.....................................
5-3 5.1-3 SITE BOUNDARY FOR GASEOUS EFFLUENTS.....................
5 4 5.1-4 SITE BOUNDARY FOR LIQUID EFFLUENTS......................
5-5
)
f, 6.2-1 0FFSITE ORGANIZATION....................................
6-3 6.2-2 UNIT ORGANIZATION.......................................
6-4 6.2-3 CONTROL ROOM AREA.......................................
6-6 O
h 7
f I
SAN ONOFRE-UNIT 3 XVII AMENDMENT NO. 22 i
a
INDEX LIST OF TABLES TABLE PAGE 1.1 OPERATIONAL M0 DES..........................................
1-7
- 1. 2 FREQUENCY N0TATION.........................................
1-8 2.2-1 REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS....
2-3 2.2-2 CORE PROTECTION CALCULATOR ADDRESSABLE CONSTANTS...........
2-5 3.3-1 REACTOR PROTECTIVE INSTRUMENTATION.........................
3/4 3-3 3.3-2 REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES..........
3/4 3-8 4.3-1 REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........................l....................
3/4 3-10 3.3-3 ENGINEERED SAFETY FEATURES' ACTUATION SYSTEM INSTRUMENTATION............................................
3/4 3-14 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES..............................
3/4 3-22 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES..................
3/4 3-27 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS..................
3/4 3-31 3.3-6 RADIATION MONITORING ALARM INSTRUMENTATION.................
3/4 3-35 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............................................
3/4 3-38 3.3 SEISMIC MONITORING INSTRUMENTATION.........................
3/4 3-43 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............
3/4 3-44 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION..................
3/4 3-46 1
4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............................................
3/4 3-47 3.3-9 REMOTE SHUTDOWN MONITORING INSTRUMENTATION.................
3/4 3-49 4.3-6 REMOTE SHUTCOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...........................................
3/4 3-50 3.3-10 ACCIDENT MONITORING INSTRUMENTATION.................
3/4 3-52 SAN ONOFRE-UNIT 3 XVIII
.-.-,_,.~_-..-.....-.-..c-
INDEX LIST OF TABLES TABLE PAGE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............................................
3/4 3-55 3.3-11 FIRE DETECTION INSTRUMENTS-MINIMUM INSTRUMENTS OPERABLE....
3/4 3-58 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION.....
3/4 3-65 4.3-8 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..................................
3/4 3-67 3.3-13 RADI0 ACTIVE GASEOUS EFF'.UENT MONITORING INSTRUMENTATION....
3/4 3-70 4.3-9 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..................................
3/4 3-72 4.4-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED OURING INSERVICE INSPECTION.......................................
3/4 4-14 4.4-2 STEAM GENERATOR TUBE INSPECTION............................
3/4 4-15 3.4-1 REACTOR COO LANT SYSTEM PRESSURE ISOLATION VALVES...........'
3/4 4-20 3.4-2 REACTOR COOLANT SYSTEM CHEMISTRY...........................
3/4 4-22 4.4-3 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS SURVEILLANCE REQUIREMENTS...............................................
3/4 4-23 4.4-4 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE...................
3/4 4-26 4.4-5 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM WITHDRAWAL SCHE 00LE...................................................
3/4 4-29 4.6-1 TENDON SURVEILLANCE........................................
3/4 6-12 4.6-2 TENDON LIFT-OFF F0RCE......................................
3/4 6-13 3.6-1 CONTAINMENT ISO LATION VALVES...............................
3/4 6-21 3.7-1 STEAM LINE SAFETY VALVES PER L00P..........................
3/4 7-2 3.7-2 MAXIMUM ALLOWABLE LINEAR POWER LEVEL-HIGH TRIP SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING OPERATION WITH BOTH STEAM GENERATORS.................................
3/4 7-3 SAN ONOFRE-UNIT 3 XIX i
I
i INDEX-LIST OF TABLES i
TABLE PAGE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM..........................................
3/4 7-9 3.7-5 SAFETY-RELATED SPRAY AND/0R SPRINKLER SYSTEMS.............
3/4 7-32 3.7-6 FIRE HOSE STATIONS........................................
3/4 7-34 4.8-1 DIESEL GENERATOR TEST SCHEDULE............................
3/4 8-7 4.8-2 BATTERY SURVEILLANCE REQUIREMENTS.........................
3/4 8-11 t
3.8-1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE 0EVICES...................................................
3/4 8-18 3.8-2 MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION BYPASS j
DEVICES PERMANENTLY 8YPASSED..............................
3/4 8-32 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM....
3/4 11-2 4.11-2 RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM...
3/4 11-9 4
3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM.............
3/4 12-3 4
3.12-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTA L S AMP LES.....................................
3/4 12-7 I
4.12-1 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION..........
3/4 12-8 83/4.4-1 REACTOR VESSEL TOUGHNESS..................................
83/4 4-8 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS......................
5-8 6.2-1 MINIMUM SHIFT CREW COMo0SITION............................
6-5 4
1 l
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I SAN ON0FRE-UNIT 3 XX AMENDME.NT NO. 22 i_
PLANT SYSTEMS 3/4.7.6 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.6 All snubbers shall be OPERABLE.
The only snubbers excluded from this requirement are those installed on nonsafety-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 /> repla'ce or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.6.g on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.6 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program, a.
Inspection Types As used in this specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity.
b.
Visual Inspections The first inservice visual inspection of snubbers shall be performed after 4. months but within 10 months of commencing POWER OPERATION and shall include all snubbers.
If less than two snubbers are found inoperable during the first inservice visual inspection, the second inservice visual inspection shall be performed 12 months i 25% from the date of the first inspection.
Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule:
No. Inoperable Snubbers Subsequent Visual per Inspection Period Inspection Perici*y 0
18 months i 25%
1 12 months i 25%
2 6 months ! 25%
3,4 124 days 25%
5,6,7 62 days i 25%
8 or more 31 days 25%
^The inspection interval shall not be lengthened more than one step at a time.
- The provisions of Specification 4.0.2 are not applicable.
SAN ONOFRE-UNIT 3 3/4 7-17 AMENDMENT NO. 22 i
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
The snubbers may be categorized into two groups:
Those accessible and those inaccessible during reactor operation.
Each group may be inspected independently in accordance with the above schedule.
c.
Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indi-cations of damage or impaired OPERABILITY and (2) attachments to the foundation or supporting structure are secure.
Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE 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 that may be generically susceptible; and (2) the affected snubber is functionally tested in the as found condition and deter-mined OPERABLE per Specification 4.7.6.e or 4.7.6.f, as applicable.
However, when a fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined inoperable and cannot be determined OPERABLE via functional testing for the purpose of estab-lishing the next visual inspection interval. All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted
{
as inoperable snubbers.
d.
Functional Tests *
\\
At least once per '18 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 tested either in place or in a bench test.
For each snubber of a type of that does not meet the functional test acceptance criteria of Specification 4.7.6.e or 4.7.6.f an additional 10% of that type of snubber shall be functionally tested until no more failures are found or until all snubbers of that type have been functionally tested.
The 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 feet of the discharge from safety relief valve.
" Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if justifiable basis for exemption is presented and/or snubber life destructive testing was performed tu qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.
SAN ONOFRE-UNIT 3 3/4 7-18 AMENDMENT NO. 22
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
Snubbers that are especially difficult to remove or in high radia-i tion zones during shutdown shall also be included in the representa-j tive sample.*
In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period.
If a 4
spare snubber has been installed in place of a failed snubber, then i
both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested.
Test results of these snubbers may not be included for the re-sampling.
e.
Hydraulic Snubbers Functional Test Acceptance Criteria **
i The hydraulic snubber functional test shall verify that:
l 1.
Activation (restraining action) is achieved within the spect-l fied range of velocity or acceleration in both tension and compression.
2.
Snubber bleed or release rate, where required, is within the specified range in compression or tension.
For snubbers i
specifically required to not displace under continuous load, the ability of the snubber to withstand load without displace-4 ment shall be verified, 1
t l
f.
Mechanical Snubbers Functional Test Acceptance Criteria **
The mechanical snubber functional test shall verify that:
1.
The force-required to initiate or maintain motion of the snubber is within the specified range in both directions of travel.
l 2.
Activation (restraining action) is achieved within the specified rarge of velocity or acceleration in both j
tension and compression.
I
" Permanent or other exemptions from functional testing for individual snubbers i
in these categories may be granted by the Commission only if justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions r.t either the completion of their fabrication or at a subsequent date.
i
- Testing methods may be used to measure parameters indirectly or parameters other than those specified if those results can be correlated to the speci-fied parameters through established methods.
SAN ONOFRE-UNIT 3 3/4 7-19 AMENDMENT No. 22 1,
i PLANT SYSTEMS j
SURVEILLANCE REQUIREMENTS (Continued) 1 j
3.
Snubber release rate, where required,4s within the l
specified range in compression or tension.
For snubbers t
specifically required not to displace under continuous i
load, the ability of the snubber to withstand load j
without displacement shall be verified.
g.
Functional Test Failure Analysis i
An engineering evaluation shall be made of each failare to meet the functional test acceptance criteria to determine the cause of the failure.
The results of this evaluation shall be used, if applicable, in selecting snubbers to be tested in an effort to determine the OPERABILITY of other snubbers irrespective of type which.'may be subject to the same failure mode.
For the snubbers found inoperable, an engineering evaluation shall be performed on the components to which the inoperable snubbers are
)
attached.
The purpose of this engineering evaluation shall be to determine if the components to which the inoperable snubbers were attached were adversely affected by the inoperability of the snubbers in order to ensure that the component remains capable of meeting the j
designed service.
I If any snubber selected for functional testing either fails to 5
lock up or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all i
snubbers of the same type subject to the same defect shall be
]
functionally tested.
This testing requirement shall be independent
[
of the requirements stated in Specification 4.7.6.e or 4.7.6.f. for
)
snubbers not meeting the functional test acceptance criteria.
I j
h.
Functional Testing of Repaired and Replaced Snubbers 1
Snubbers which fail the visual inspection or the functional test I
acceptance criteria shall be repaired or replaced.
Replacement snubbers and snubbers which have repairs which might affect the
.i functional test result shall be tested to meet the functional test criteria before installation in the unit.
These snubbers shall have met the acceptace criteria subsequent to their most recent service, 1
and the functional test must have been performed within 12 months j
before being installed in the unit.
i I
l SAN ONOFRE-UNIT 3 3/4 7-20 AMEN 0 MENT NO. 22 i
.s i
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 1 1.
Snubber Service Life Monitoring l
A record of the service life of each snubber, the date at which the a
designated service life commences and installation and maintenance i
records on which the designated service life is based shall be main-tained as required by Specification 6.10.2.1.
i Concurrent with the first inservice visual inspection and at least once per 18 months thereafter, the installation and maintenance records for each snubber shall be reviewed to verify that the j
indic(:ed service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review.
J If the indicated service life will be exceeded prior to the next I
scheduled snubber service life review, the snubber service life shall be reevaluated or the snub'er shall be replaced or recondi-o l
tioned so as to extend its service life beyond the date of the next scheduled service life review.
This reevaluation, replactment or j
reconditioning shall be indicated in the records, f
i J.
Refueling Outage Inspections During each refueling outage an inspection shall be performed of snubbers attached to sections of safety systems piping that have ex-perienced unexpected, potentially damaginq transients as determined 4
j from a review of operational data and a visual inspection of the systems.
In addition to satisfying the visual inspection acceptance criteria, freedom of motion of mechanical snubbers shall be verified l
using one of the following:
(i) manually induced snubber movement; (ii) evaluation of in place snubber piston setting; (iii) stroking i
the mechanical snubber through its full range of travel.
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l SAN ONOFRE-UNIT 3 3/4 7-21 AMEN 0 MENT NO. 22
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e SAN Ofl0FRE-UNIT 3 3/4 7-24 AMENDMENT NO. 22
PLANT SYSTEMS BASES 3/4.7.6 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 event initiating dynamic loads.
Snubbers excluded from this inspection program are those installed on nonsafety 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.
For visual inspection snubbers are categorized into two (2) gronos, those accessible and those inaccessible during reactor operation.
For functional testing, snubbers are categorized into types by design and manufacturer, irrespective of capacity.
For example, Pacific Scientific snubbers are divided into four types corresponding to different design features:
PSA 1/4 and 1/2 are one type; PSA 1, 3, and 10 are another; PSA 6 is another; and PSA 35 and 100 are a fourth type.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems.
Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of ir. operable snubbers found during an inspection.
Inspections performed before that interval has elapsed may be used as 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 (nominal time less 25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.
To provide assurance *of snubber functional reliability, a representative sample of the installed snubbers will be functionclly tested during plant shutdowns at 18 month intervals.
Hydraulic snubbers and mechanical snubbers may each be treated as a dif-ferent entity for the above surveillance programs.
SAN ONOFRE-UNIT 3 B 3/4 7-5 AMENDMENT N0. 22 i
l l
PLANT SYSTEMS BASES
{
SNUBBERS (Continued)
The service life of a snubber is evaluated via marufacturer input and information through consideration of the snubber service conditions and 1
j associated installation and maintenance records,(newly installed snubber, seal j
replaced, spring replaced, 'iii high radiation area, in high temperature area, i
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 ano 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.
3/4.7.7 SEALED SOURCE CONTAMINATION l
The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for i
plutonium. This limitation will ensure that leakage from byproduct, source, r
and special nuclear material sources will not exceed allowable intake values.
1 4
Sealed sources are 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 4
required to be tested more often than those which are not.
Sealed sources
~
+
which are continuously enclosed within a shielded mechanism (i.e. sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shield mechanism.
l 3/4.7.8 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is l
located.
The fire. suppression system consists of the water system, spray and/or sprinklers, and fire hose stations.
The collective capability of the i
fire suppression systems is adequate to minimize potential damage to safety i
j related equipment and is a major element in the facility fire protection t
program.
t I
In the event that portions of the fire suppression systems are j
inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service.
When the inoperab'e fire fighting equipment is intended for use as a backup means of fire suppression, a longer period of time is allowed to provide an' alternate means of fire fighting than if the inoperable equipment is the primary means of fire suppression.
The surveillance requirements provide assurance that the minimum OPERABILITY requirements of the fire suppression systems are met.
l SAN ON0FRE-UNIT 3 8 3/4 7-6
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j i
~.
ADMINISTRATIVE CONTROLS l
6.10.1 The following records shall be retained for at least five years:
a.-
Records and logs of unit operation covering time interval at each power level.
b.
Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety, c.
All REPORTABLE OCCURRENCES submitted to the Commission.
d.
Records of surveillance activities; inspections and calibrations required by these Technical Specifications.
e.
Records of changes made to the procedures required by Specification 6.8.1.
f.
Records of radioactive shipments.
g.
Records of sealed source and fission detector leak tests and results.
h.
Records of annual physical inventory of all sealed source material of record.
6.10.2 The following records shall be retained for the duration of the Unit j
Operating License:
a.
Records and drawing changes reflecting unit design modifications i
made to systems and equipment described in the Final Safety Analysis
- Report, b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
c.
Records of radiation exposure for all individuals entering radiation control areas, i
d.
Records of gaseous and liquid radioactive material released to the environs.
e.
Records of transient or operational cycles for those unit components l
identified in Table 5.7-1.
l f.
Records of reactor tests and experiments.
g.
Records of training and qualification for current members of the unit staff.
SAN ONOFRE-UNIT 3 6-23
ADMINISTRATIVE CONTROLS h.
Records of in-service inspections performed pursuant to these Technical Specifications.
i.
Records of Quality Assurance activities required by the QA Manual, j.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k.
Records of meetings of the OSRC and the NSG.
1.
Records of the service lives of all snubbers within the scope of l
Technical Specification 3/4.7.6 including the date at which the ser-vice life commences and associated installation and maintenance records.
m.
Records of secondary water sampling and water quality.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Exposure Permit (REP)*.
Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.
- Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the REP issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise following approved plant radiation protection procedures for entry into high radiation areas.
SAN ONOFRE-UNIT 3 6-24 AMENDMENT N0. 22