ML20010F959

Proposed Tech Specs 3/4.7.10 Re Snubbers & 6.11 & 6.12 Re Administrative Controls

ML20010F959
Person / Time
Site:	North Anna
Issue date:	09/10/1981
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20010F958	List: ML20010F957 ML20010F959 ML20010F964
References
NUDOCS 8109150160
Download: ML20010F959 (8)

Text

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PLANT SYSTEMS 3/4.7.10 SNUBBERS LIMITING CONDITION FOR OPERATION _

3.7.10 All snubbers listed.in Tables 3.7-4a and 3.7-4b shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4. (MODES 5 and 6 for snubbers located c,r, systems required OPERABLE in these 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 4.7.10.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.

SURVEILLANCE REQUIREMENTS 4.7.10 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.

a. Visual Inspections The first inservice visual inspection of snubbers shall be performed after four months but within 10 months of commencing POWER OFERATION and shall include all snubbers listed in Tables 3.7-4a and 3.7-4b.

If less than two (2) snubbers are found inoperable during the first inservice viaal 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 nerformed in accordance with the following schedule:

No. Inoperable Snubbers Subsequent Visual ,

per Inspection Period Inspection Period

• 0 18 months i 25%

1 12 months i 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.

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, The inspection interval shall not be lenthened more than one step at a time.

The provisions of Specification 4.0.2 are not applicable.

NORTH ANNA - UNIT 1- 3/4 7-28 8109150160 810910 PDR ADOCK 05000338 P PDR

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

b. Visual Inspq y.on Acceptance Criteria Visual inspectiQs shall verify (1) that there ar2 no visual indica-tions of damage or impaired OPERABILITY, (2) attachments to the founda" or supporting structure are secure, and (3) in those locat. .b where snubber movement can be manually induced without

" disconnecting the snubber, that the snubber has freedom of mcvement and is not frozen up. Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purposa of establishing the next visual inspection interval, providing 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 determined OPERABLE per Specifi-cations 4.7.10.d and 4.7.1( a. However, when the 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 establishing the next visual inspection interval. All inubbers connected to an inoperable common hydraulic fluid reservior shall be counted as inoperable snubbers.

c. Functional Tests At least once per 18 months during shutdown, a representative sapple ofthatnumberofsnubberswhichfollowstheexpression35[1+j), -

where c=2 is the allowable number of snubbers not meeting the acceptance criteria selected by the operator, shall be functionally tested either in place or in a bench test. For each number of snubbers above c which does not meet the functional test acceptance criteria of Specification 4.7.10.d or 4.7.10.e, and additional sample 2

selectedaccordingtotheexpression35(1+j)(g l)2 (a - c) shall be functionally tested, where a is the total number of snubbers found inoperable during the functional testing of the representative sample.

Functional testing shall continue according to the expression b[35(1+j)2]wherebisthenumberofsnubbersfound inoperable in the previous re-sample, until no additional inoperable snubbers are found within a sample or until all snubbers in Table 3.7-4a and 3.7-4b have been functionally tested.

NORTH ANNA - UtlIT 1 3/4 7-29a

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of saubbers. At least 25% of the snubbers in the regtesentative sainple 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 a safety relief valve.

Snubbers icentified in Tables 3.7-4a and 3.7-4b as "Especially Difficult to Remove" or in "High Radiation Zones During Shutdown" shall also be included in the representative sample.* Tables 3.7-4a and 3.7-4b may be used jointly or separately as the basis for the sampling plan.

In addition to tne regular sample, snubbers which failed the previous functional test shall be retested dur!.1 the next test period. If a spare snubber has been installed in pla w 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 resuits of these snubbers 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 caust will be evaluated and if caused by manufacturer or design defic'ency ill snubbers of the same design subject to the same defect sb ' se functionally tested. This testing requirement shall be endent of the requirements stated above for snubbers no me' , .

functional test acceptance crite.-ia.

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 snubber (s) in order to ensure that the supported component remains capable of meeting the design service.

A 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.

NORTH ANNA - UNIT 1 3/4 7-29b

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

d. Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that:

1. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compressio>.

2. Snubber bleed, or release rate, wl.are 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.

e. Mechanical Snubbers Functional Test Acceptance 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. Drag force shall not have increased more than E3% since the last functional test.

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 tensien. For snubbers specifically required n,t to displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.

f. Snubber Service Life Monitoring A record of the service life of each snuhber, the date at which the designatea service life commences and the installation and mainte-l nance records on which the designated service life is based shall be l

maintained as required by Specification 6.10.2.

Concurrent with the first inservice visual inspection and at least once per 18 months thereafter, the installation and maintenance records for each snubber listed in Tables 3.7-4a and 3.7-4b shall be reviewed to verify that the indicataa service life has not been exceeded or will not be exceeded prior to the next scheduled snubber NORTH ANNA - UNIT 1 3/4 7-29c

PLANT SYSTEMS SURVEILLANCE REQUIREMFNTS (Continued) service life review. If the indicated service life will be exceeded prior to the next scheduled snubber service life review, 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 service life review. This reevaluation, '

replacem2nt or reconditioning shall be indicated in the records.

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ADMINISTRATIVE CONTR0LS

a. Records and drawing changes reflecting facility design moaifi-cations 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 far.ility radiation and contamination surveys.

d. " Records of radiation exposure for all individuals entering radiation control areas.

e. Records of gaseous and liquid radioactive material released to the environs.

f. Records of transient operational cycles for those facility components identified in Table 5.9-1.

g. Records of reactor tests and experiments.

h. Records of training and qualification for current members of the plant staff.

i. Records of in-service inspections performed pursuant to these Technical Specifications.

j. Records of Quality Assurance activities required by the QA Manual.

k. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

1. Records of meetings of the SNSOC.

m. Records of meetings of the System Nuclear Safety and Operating Committee to issuance of Amendment No. 30.

n. Records of the service lives of all hydraulic and mechanical snubbers listed on Tables 3.7-4a and 3.7-4b including the date at which the service life commences and associated installation and maintenance records.

o. Records of secondary water sampling and water quality.

p. Records of Environmental Qualification which are covered under the provisions of paragraph 6.13.

NORTH ANNA-UNIT 1 6-21 Amendment No.

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ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared con-sistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radia-tion 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 Work Ferait.* 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.

c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.

This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency cpecified by the facility Health Physicist in the Radiation Work Permit.

I 6.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than l 1000 mrem /hr. In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or the Plant Health Physicist.

" Health Physics personnel shall be exempt from the RWP issuance require-i ment during the performance of their assigned radiat'.an protection duties, provided they comply with approved radiation protection procedures for tentry into high radiation areas.

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NORTH ANNA - UNIT 1 6-22 Amendment No.

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6 ATTACHMENT 2 SUPPLEMENT TO PROPOSED TECHNICAL SPECIFICATION CHANGE UNIT 2 i

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