ML20127M903

Amend 41 to License NPF-12,modifying Tech Specs to Indicate That All Snubbers on Sys Required for Safe Shutdown/Accident Mitigation Shall Be Operable & to Delete Tables 3.7-4a & 3.7-4b

ML20127M903
Person / Time
Site:	Summer
Issue date:	05/06/1985
From:	Adensam E Office of Nuclear Reactor Regulation
To:
Shared Package
ML20127M906	List: ML20127M903 ML20127M951
References
NUDOCS 8505230386
Download: ML20127M903 (12)

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' UNITED STATES NUCLEAR REGULATORY COMMISSION

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SOUTH CAROLINA ELECTRIC & GAS COMPANY 7

SOUTH CAROLINA PUBLIC SERVICE AUTHORITY F'

DOCKET NO. 50-395 ~

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. VIRGIL C. SUMMER NUCLEAR STATION. UNIT NO. 1

-AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.41 j'

License No. NPF-12

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1.

The Nuclear Regulatory Comission _(the Comission) has found that:

j A.

The application'for amendment ho the Virgil C. Sumer Nuclear Station.

Unit No. 1-(the facility) Facility Operating License No. NPF-12 filed by the South Carolina Electric & Gas Company acting for itself and

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South Carolina Public Service Authority (the licensees), dated November 16, 1983, as amended December 14, 1984, complies with the standards and requirements of the Atomic Energy _Act of 1954,~ as amended (the Act) and the Commission'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; 4

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C.

There is reasonable assurance: (i) that the activities authorized by i

this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted b

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 common defense and security or to the health and safety of the public;.

E.

The issuance of this license amendment is in accordanc'e with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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Accordingly, the license-is hereby 6 mended by page changes to the Technical 1

Specifications as indicated in the attachments to this license amendment and paragraph 2.C(2) of Facility Operating License No. NPF-12 is hereby amended

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to read as follows:

(2) Technical Specifications t(.

P The Technical Specifications contained in Appendix A, as revised through Amendment No. 41 are hereby incorporated into this license. South Carolina Electric & Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

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3. -This license amendment is effective as of its date of issuance.

t' FOR THE NUCLEAR REGULATORY COMMISSION

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W Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing

Enclosure:

l Technical Specification Changes I

Date of Issuance:

May 6, 1985 1

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ATTACHMENT TO LICENSE AMENDMENT NO.41 FACILITY OPERATING LICENSE NO. NPF-12 DOCKE'T NO. 50-395 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 areas of change. The corresponding overleaf pages

--..are also provided to maintain document completeness.

Amended Overleaf Page Page 3/4 7-16 3/4 7-17 3/4 7-18 3/4 7-21 3/4 7-22 B3/4 7-4 83/4 7-5 B3/4-7-5 6 - 20 h

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~ PLANT SYSTEMS' 3/4.7.7 SNUB 8ERS

' LIMITING CONDITION FOR OPERATION

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3.7'7 'All' snubbers on' systems required for safe shutdown / accident mitigation shall be OPERABLE. This includes safety and non-safety related snubbers.on systems used to protect the code boundary and to~ ensure the structural integ-rity of these systems under dynamic loads.

4 APPLICA8ILITY:.' MODES 1, 2, 3 and 4.

MODES 5 and 6 for snubbers located on

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. systems required OPERA 8LE in those MODES.

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~ ACTION:

p 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 t

iaoperable snubber (s) to.0PERA8LE status and perform an engineering evaluation per Specification 4.7.7.g on the attached component or declare'the attached

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system inoperable and follow the appropriate ACTION statement for that system.

SURVEILLANCE REQUIREMENTS i

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4.7.7 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.

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Inspection Types As used in this specification, type of snubber shall mean bbers of the same design and manufacturer, irrespective of city.

b.

Visual Inspections i

The first inservice visual inspection of eacbtype of snubber shall-be performed after 4 months but within 10 months of commencing POWER OPERATION and shall include all snubbers defined in Section 3.7.7.

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If less than two snubbers of'each type 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 i

first inspection.

Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule:

.No. Inoperable Snubbers of each Subsequent Visual,

type per Inspection Period Inspection Period" O

18 months 1 25%

i-1 12 months 1 25%

6 months t 25%

2 124 days t 25%

3,4 5,6,7 62 days t 25%

i 31 days t 25%

8 or more "The inspection interval for each type of snubber ; hall not be lengthened i

more than one step at a time unless a generic problem has been identified l

and corrected; in that event the inspection interval may be lengthened one j'

step the first time and two steps thereafter if no inoperable snubbers of that type are found.

1. The provisions of Specification 4.0.2 are not applicable.

SUMMER - UNIT 1 3/4 7-16 Amendment No. 41

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PLANT SYSTEMS t

SURVEILLANCE REQUIREMENTS (Continued)

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Refueling Outage Inspections At least'once per 18 months an inspection shall be performed of all

.the snubbers defined in Section 3.7.7 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. ir:spection of the systems.

In addition to satisfying the-visual inspection acceptanca criteria, freedom of motion of mechanical snubbers shall be verified using at least one of the-

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following:

(i) manually induced snubber movement; (ii) evaluation of in place snubber piston setting; or (iii) stroking the mechanical

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snubber through it's full range of travel.

d.

Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indications 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 snubbert irrespective of type that may be generically susceptible; and (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE-per Specifications 4.7.7.f.

When a fluid port of a hydraulic snubber is found to be uncovered the snubber shall be declared inoperable and shall not be determined OPERABLE via functional testing unless the test is started with the piston in the as found setting, extending the piston rod in the tension mode direction. All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.

e.

Functional Tests During the first refueling shutdown and at least once per 18 months thereafter during shutdown, a representative sample of either:

(1) 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 4.7.7.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, or (2) A representative sample of each type of snubber shall be functionally tested in accordance with Figure 4.7-1, "C" is the total number of snubbers of a type found not meeting the acceptance requirements of Specification 4.7.7.f.

The cumulative number of snubbers of a type tested is denoted by "N."

At the end of each day's testing, the new values of "N" and "C" (previous day's total plus current day's increments) shall be plotted on Figure 4.7-1.

If at any time the point plotted falls in the " Reject" region all snubbers of that type shall be functionally tested.

If at any time the point plotted falls in Sup04ER - UNIT 1 3/4 7-17 Amendment No. 41 f

re PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) e.

Functional Tests (Continued) the " Accept" region testing of that type of snubber may be

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terminated. -When the point plotted lies in the " Continue Testing" region, additional snubbers of that type shall be tested until the point falls in the " Accept" region or the " Reject" region, or all the snubbers of that type have been tested.

The representative sample selected for functional testing shall include the various configurations, operating environments, and the range of size and capacity of' snubbers of each type.- The represen-tative sample shall be weighted to include more snubbers from severe service areas such as near heavy equipment.

Snubbers placed in the same location as snubbers which failed the pr'evious functional test shal.1 be included in the next test lot if the failure analysis shows that failure was due to location.

f.

Functional Test Acceptance Criteria The snubber functional test shall verify that:

1..

Activation (restrainin; action) is achieved within-the specified range in both tension and compression', except that inertia dependent, acceleration limiting mechanical snubbers, may be tested to verify only that activation takes place in both directions of travel.

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Snubber bleed, or release rate where required, is present in both tension and compression, within the specified range.

3.

Where required, the force required to initiate or maintain motion'of the snubber is within the specified range in both direction of travel.

4.

For snubbers specifically required not'to displace under continuous load, the ability of the snubber to withstand load without displacement.

5.

Fasteners for attachment of the snubber to the component and to the snubber anchorage are secure.

Testing methods may be used to measure parameters indirectly or parameters other than those specified if those results can be correlated to the specified parameters through established methods.

g.

Functional Test Failure Analysis An engineering evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause of the failure.

The results of this evaluation shall be used, if applicable,

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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.

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SUMMER - UNIT 1 3/4 7-18 i

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PLANT SYSTEMS f

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i SUMER - UNIT 1 3/4 7-21 Amendment No. 41 l'

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SUP9tER - UNIT 1 3/4 7-22 Amendment No. 41 f

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. PLANT SYSTEMS BASES ULTIMATE HEAT SINK (Continued)

The'11mitations on minimum water level and maximum temperature are based on providing a 30 day cooling water supply to safety related equipment without exceeding their design basis temperature and is consistent with the

-recommendations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear

. Plants", March 1974.

'3/4.7.6 CONTROL ROOM NORMAL AND EMERGENCY AIR HANDLING SYSTEM The OPERA 81LITY of the control room ventilation system ensures that

1) the ambient air temperature does not' exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and~following all credible accident conditions.

The OPERA 81LITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room.'to 5 rem or less whole body, or its equivalent.

This limitation is consistent with the requirements of General Design Criteria 19 of Appendix "A", 10 CFR 50..

3/4.7.7 SNUB 8ERS All snubbers on systems required for safe shutdown / accident mitigation shall be OPERA 8LE.

This includes safety and non-safety related snubbers on systems used to protect the code boundary and to ensure the structural integrity of these systems under dynamic loads.

Snubbers are classified and grouped by design and manufacturer but not by size.

For example, mechanics 1 snubbers utilizing the same design features of the 2 kir. 10 kip and 100 kip capacity manufactured by company "A" are of the same type. The same design mechanical snubber manufactured by company "8" for the purposes of this specification would be of a different type, as would hydraulic snubbers from either manufacturer.

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 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 re, quire a shorter inspectiuo interval will override the previous schedule.

SUMER - UNIT 1 8 3/4 7-4 Amendrent No. 41

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PLANT SYSTEMS BASES SNUBBERS (Continued)

To provide assurance of snubber functional reliability one of two sampling and acceptance criteria methods are used:

1) functionally test 10 percent of a type of snubber with an additional 10 percent tested for each functional testing failure, or

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2) functionally test a sample size and determine sample acceptance or rejection using Figure 4.7-1.

Figure 4.7-1 was developed using "Wald's Sequential Probability Ratio Plan" as described in " Quality Control and Industrial Statistics" by Acheson J. Duncan.

The service life of a snubber is established 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.

Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commissicn if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the snubber for the applicable design conditions at either the completion of their fabrication or at a subsequent date.

Snubbers so exempted shall be listed in Section 3.7.7 with footnotes indicating the extent of the exemptions.

4 SUMMER - UNIT 1 8 3/4 7-5 Amendment No. 41 I

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I PLANT SYSTEMS BASES 3/4.7.8 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 within a shielded mechanis.a (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 shielded mechanism.

3/4.7.9 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression occurring in any capability is available to, confine and extinguish fires portion of the facility where safety-related equipment is located.

The fire suppression system consists of the water system, spray I

and/or' sprinklers, CO, fire hose stations, and yard fire hydrants.

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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.

In the event the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant.

The requirement for a twenty-four hour report to the Commission provides for prompt evaluation of the acceptability of the corrective measures to pro. vide adequate fire suppression capability for the continued protection of the nuclear clant.

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O SUMMER - UNIT 1 8 3/4 7-6 t

ADMINISTRATIVE CONTROLS 3

1.

Records of Quality Assurance activities as specified in the NRC's approved SCE&G position on Regulatory Guide 1.88, Rev. 2, October 1976.

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Records.of reviews performed for changes made to procedures or

equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

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Records of meetings of the PSRC and the NSRC.

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Records of the service lives of all hydraulic and mechanical snubbers defined in Section 3.7.7 including the date at which the l

service life commences and associated installation and maintenance records.

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Records of secondary water sampling and water quality.

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Records of analysis required by the radiological environmental monitoring program.

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 personne1' radiation exposure.

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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 mres/hr but less than 1000 aren/hr shall be barricaded and conspicuously posted'as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).* 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 radfation 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, c,

A health physics qualified individual (i.e., qualified in radiation protection procedures) 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 Work Permit.

" Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they otherwise comply with approved radiation protection procedures for entry into high radiation areas.

SUPMER - UNIT 1 6-20 Amendment No. 41

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