ML20245A190

Amend 110 to License DPR-54,revising Tech Specs by Removing Tabular Listing of Snubbers as Suggested by Generic Ltr 84-13

ML20245A190
Person / Time
Site:	Rancho Seco
Issue date:	06/09/1989
From:	Knighton G Office of Nuclear Reactor Regulation
To:
Shared Package
ML20245A185	List: ML20245A183 ML20245A190 ML20245A199
References
GL-84-13, NUDOCS 8906210137
Download: ML20245A190 (14)

Text

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f, - j,, UNITED STATES c NUCLEAR REGULATORY COMMISSION r, .

usamorow. o. c. rossa )

\....J SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE I

I Amendment No.110 i l License No. DPR-54 )i

1. The Nuclear Regulatory Comission (the Comission) has found that:

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A. The application for amendment by Sacramento Municipal Utility

, District (the licensee) dated October 8,1986, as revised September 8,1987 complies with the standards and requirements '

i of the Atomic Energy Act of 1954, as amended (the Act), and the  !

Comission's regulations set forth in 10 CFR Chapter I; '

B. The facility will operate in conformity with the appitcation, the l

provisions of the Act, and the regulations of the Comission; C. Thereisreasonableassurance(1-)thattheactivitiesauthorizedby l this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted i in compliance with the Comission's regulations; i D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and '

1 E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have  !

been satisfied.

l 8906210137 DR ApocM 05000312 890609 '

• PNU,

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2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-54 is hereby amended to read as follows:

(2)TechnicalSpecifications The Technical Specifications contained in Appendices

• A and B, as revised through Amendment No.110. are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment shall become effective within 30 days of the issuance date. The implementation delay is provided to allow time for modification of affected procedures and promulgation of the changes to personnel.

FOR THE NUCLEAR REGULATORY COMMISSION pb' -

George . Knighton irector Project Directorate V.

Division of Reactor Projects III,

- IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: June 9, 1989 e

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.I I ATTACHMENT TO LICENSE. AMENDNENT N0.110 I FACILITY.0PERATING LICENSE.NO..DPR.54 ,

t DOCKET NO. 50-312 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical. lines indicating the area of change.

l Remove Insert I iX iX X X 3-51 3-51 3-51a 3-51a 3-51b ---

3-51c ---

3-51d ---

3-51e ---

4-47 4-47 4-47a 4-47a 4-47b ,~'

4-47b 4-47c 4-47c 4-47d 4-47d 4-47e 4-47e 6-14 6-14

, RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS 4 LIST OF TABLES IAhli EAnt 1.2-1 OPERATIONAL MODES 1-2c 1.9-1 FREQUENCY NOTATION 1-10 2.3-1 REACTOR PROTECTION SYSTEM TRIP SETTING LIMITS 2-9 3.0-1 APPLICABILITY OF SPECIFICATIONS 3.0.3 AND 3.0.4 3-Oa 3.3-1 PRIMARY COOLANT SYSTEM PRESSURE ISOLATION VALVES 3-22b

3. 5.1- 1 INSTRUMENTS OPERATING CONDITIONS 3-27 3.5.5-1 ACCIDENT HONITORING INSTRUMENTATION OPERABILITY

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3-38e REQUIREMENTS 3.5.7-1 EMERGENCY SHUTDOWN INSTRUMENTATION 3-38j 3.6-1 SAFETY FEATURES CONTAINMENT ISOLATION VALVES 3-40 3.7-1 VOLTAGE PROTECTION SYSTEM RELAY TRIP VALUES 3-41a 3.7-2 VOLTAGE PROTECTION SYSTEM LIMITING CONDITIONS 3-43b' 3.12-1 DELETED 3.14-1 FIRE DETECTION f STRUMENTS FOR SAFETY SYSTEMS 3-55 3.14-2 INSIDE BUILDING FIRE HOSE STATIONS 3-56b,c 3.14-3 CARBON DIOXIDE SUPPRESSION ZONES 3-56d e 3.14-4 FIRE HOSE STATIONS 3-57a,b 3.15-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3-61 3.16-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 3-64 3.22-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3-83 I

3.22-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS 3-86 I IN ENVIRONMENTAL SAMPLES )

3.29-1 METEOROLOGICAL MONITORING INSTRUMENTATION 3-95 4 4.0-1 APPLICABILITY OF SPECIFICATIONS 4.0.2 AND 4.0.3 4-Oa 4.1-1 INSTRUMENT SURVEILLANCE REQUIREMENTS 4-3 1

Amendment No. 88, 80, 85, 87, 88, 94, 97, 98, 110 ix l

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS LIST OF TABLES 1 16 tift Elgt 4.1-2 HINIMUM EQUIPMENT TEST FREQUENCY 4-8 4.1-3 MINIMUM SAMPLING FREQUENCY 4-9 4.2-1 CAPSULE ASSEMBLY HITHDRAHAL SCHEDULE AT DAVIS-BESSE 1 4-12b 4.6-1 DIESEL GENERATOR TEST SCHEDULE 4-34j

4. 6. -2 ADDITIONAL RELIABILITY ACTIONS 4-34k 4.14-1 DELETED l '

4.17-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED

• 4-56 l DURING INSERVICE INSPECTION 4.17-2A STEAM GENERATOR TUBE INSPECTION 4-57 i 4.17-2B STEAM GENERATOR TUBE INSPECTION (SPECIFIC LIMITED AREA) 4-57a 4,17-3 i OTSG AUXILIARY FEEDWATER HEATER SURVEILLANCE 4-57b.c 4.19-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 4-64 i

SURVEILLANCE REQUIREMENTS 4.20-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 4-66 SURVEILLANCE REQUIREMENTS 4.21-1 RADIOACTIVE LIQUID HASTE SAMPLING AND ANALYSIS PROGRAM 4-70 1

i 4.21-2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 4-72b 4.22-1 RADIOACTIVE GASEOUS HASTE SAMFLING AND AN LYSIS PROGRAM 4-75 1 4 26-1 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD) 4-84 4.28-1 EXPLOSIVE GAS MIXTURE INSTRUMENTATION SURVEILLANCE REQUIREMENTS 4-8B 4.34-1 METEOROLOGICAL MONITORING INSTRUMENTATION 4-94 6.2-1 MINIMUM SHIFT CREW COMPOSITION 6-2 i l

I Amendment No. 28. 66. 76. 88. 94. ff, 97, 98 110 '

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.12 SNUBBERS i

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.

l Aeolicability i

When the reactor system is at HOT SHUTDOWN, HOT STANDBY, STARTUP or POWER OPERATION. During COLD SHUTDOHN, REFUELING SHUTDOHN and REFUELING OPERATION, only snubbers located on systems required to ,

be OPERABLE for nuclear safety. i Action I 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 /> either:

1. replace or restore the inoperable snubber (s) to OPERABLE status I and perform an engineering evaluation per Specification 4.14c on the supported component, or

2. declare the supported system inoperable and follow the ~

appropriate specification statement for that system, or

3. modify supports.such that the supported component and the I

supports will be OPERABLE and within the design basis of the i plant. All such changes will be subject to the provisions of  !

10 CFR 50.59 and will be reflected in the records required by j Specification 4.14f. Also perform an engineering evaluation of '

the as-found condition per Specification 4.14c.

Bases 1

Snubbers are designed to prevent unrestrained pipe motion under dynamic loads as might occur during an earthquake or severe transient, while allowing normal thermal motion during sttrtup and 3 shutdown. The consequence of an inoperable snubber is an increase '

in the probability of structural damage to piping as a result of a seismic or other event initiating dynamic loads. It is therefore required that all snubbers required to protect the primary coolant system or any other safety system or component be OPERABLE. l 1

Amendment No. 77, 110 3-51 i

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS

, Limiting Conditions for Operation l

TABLE 3.12-1 SAFETY RELATED HYDRAULIC SNUBBERS l

This Table has been deleted.

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Amendment No. 77, 110 3-51a

.' , RANCHO SECO UN8T 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.14 SNUBBERS Each snubber shall be demonstrated OPERABLE by performance of the following:

a. Viseal Insoettions The first inservice visual inspection of snubbers shall be performed after four months but within 10 months of commencing POWER OPERATION and shall include all snubbers. If less than l two (2) snubbers are found inoperable during the first inservice visual inspection, the second inservice visual inspection shall be performed 12 months 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 Der Insoection Period Insoection Period

• O 18 months : 25%

1 12 months : 25%

2 6 months 25%

3, 4 124 days : 25%

5, 6, 7 62 days : 25%

8 or more 31 days : 25%

The snubbers niay 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,

b. Visual Insoettion Acceotance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired operability, (2) attachments to the foundation or supporting structure are secure, and (3) in those locations where snubber movement can be manually induced without. disconnecting the snubber, that the snubber has freedom of movement and is not frozen up. Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose 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 ba generically susceptible; and (2) the affected snubber is

• The inspection interval shall not be lengthened more than one step at a time and Definition section 1.9 does not apply.

Amendment No. 77,110 4-47

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards l functionally tested in the as found condition and determined l OPERABLE per Specification 4.14d or 4.14e. However, when the l fluid reservoir of a hydraulic snubber is found to have the reservoir port uncovered, the snubber shall be determined inoperable and may be determined OPERABLE via functional testing if the test is started with the piston in the as-found setting, extending the piston rod in the tension mode direction. j l

c. Functional Tests l

At least once per REFUELING INTERVAL, a representative sample (107, of the total of each type of snubber (mechanical or hydraulic) in use in the plant) shall be functionally tested either in place or in a bench test. For each snubber that does not meet the functional test acceptance criteria.of Specification 4.14d or 4.14e, an additional 107. of that type of j snubber (mechanical or hydraulic) shall be functionally tested.  !

The representative sample selected for functional test sample 1 plans shall be randomly selected from the snubbers of each type i and reviewed before beginning the testing. Review shall ensure l l as far as practicable that the selected snubbers are 1 representative of the various configurations, operating -

environments, and the range of size and capacity of snubbers of each type (mechanical or hydraulic).

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In addition to the regular sample, snubbers which failed the previous functional test and were reinstalled 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 l I snubber (if it is repaired and installed in another position)

' and the spare snubber shall.be retested. These snubbers shall not be included in the random sample and the results of these tests shall not be used to determine additional testing requirements.

If any snubber selected for functional testing either fails to i lockup or fails to move, i.e., frozen in place, the cause will  ;

be evaluated and if caused by manufacturer or design deficiency l all snubbers of the same design subject to the same defect i shall be functionally tested. This testing requirement shall i be independent of the. requirements stated above for snubbers  ;

not meeting the functional test acceptance criteria.

l Amendment No. 77,110 4-47a 1

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RANCHO SECO UNIT 1 1 TECHNICAL SPECIFICATIONS I Surveillance Standards 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 J 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 designed service.  !

d. Hydraulic Snubbers Functional Test Accentance Critnig 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 compression.

2. Snubber bleed, or release rate, where required, is within 1 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 Snpbber Functional Test Accentance Criteria -

The mechanical snubber functional test shall verify that:

l 1. Theforcethltinitiatesfreemovementofthesnubberrod in either tension or compression is less than the specified maximum drag force. Drag force shall not have increased more that 50% 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-tension. For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.

f. Snubber Service Life Monitorina I l A record of the service life of each snubber, the date at which the designated service commences and the installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2n.

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Amendment No. 77, 110 4-47b

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS'  !

Surveillance Standards  ;

Concurrent with the first inservice visual inspection and at least once per REFUELING INTERVAL 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  ;

review, the snubber service life shall be re-evaluated or the-snubber shall be replaced or reconditioned so as to extend its j service life beyond the date of the next scheduled service life- '

review. This re-evaluation, replacement or reconditioning shall be indicated in the records, i

Bases 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.

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 fouad 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 l such early inspections performed before the original required time interval i has elapsed (nominal time less 25%) may not be used to lengthen the required j inspection interval. Any inspection whose results require a shorter  !

inspection interval will override the previous schedule.  !

When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable. Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection, or are similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration.

l l Amendment No. 71, 110 4-47c

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.i RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards j Hhen a snubber is found inoperable,' an engineering evaluation is performed, in addition to the determination of the snubber mode of failure, in order to 1 determine if any safety-related component or system has been adversely l affected by the inoperability of the snubber. The engineering evaluation l shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.

To provide assurance of snubber functional reliability, a 10% sample of the installed snubbers will be functionally tested during plant shutdowns at-REFUELING INTERVALS. Observed failures of these sample snubbers shall I require functional testing of additional units.

Hydraulic snubbers and mechanical snubbers will each be treated as a different entity for the above surveillance programs. l l

The service life of a snubber is evaluated via manufacturer input and )

information through consideration of the snubber service conditions and I associated installation and maintenance records (newly installed snubber, )

j seal replaced, spring replaced, in high radiation area, in high temperature  !

, area, etc.). The requirement to monitor the snubber service life is  !

l included to ensure that the snubbers periodically undergo a performance j evaluation in view of their age and operating conditions. These records l will provide statistical basis for future consideration of snubber service i life. The requirements for the maintenance of records and the snubber ,

service life review are not intended to affect plant operathn. '

ItistheintentofSpecif) cation 4.14toreplace/reconditionand 1 functionally test all snubbers within a ten refueling interval period. In

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no case will re-evaluation of any snubber's service life allow more than ten i

refueling intervals to pass before replacement / reconditioning and functional testing.

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Amendment No. 77, 110 4-47d l

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, i RANCHO SECO UNIT 1 i TECHNICAL SPECIFICATIONS  ;

i Limiting Conditions for Operation i i

TABLE 4.14-1 l DESIGNATED SAFETY RELATED HYDRAULIC SNUBBERS FUNCTIONALLY TESTED ONLY AS REOUIRED BY THE SNUBBER SEAL REPLACEMENT PROGRAM I

This Table has been deleted. .

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l Amendment No. 77,110- '

4-47e 1 1

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls

b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c. Records of facility. radiation and contamination surveys.

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

? e. Records of gaseous and'11guid radioactive material released to the environs.

f. Records of transient or operational cycles for those facility components designed.for a limited number of transients or cycles.

g. Records of training and qualification for current members of the' plant operating staff.

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

1. Records of Quality Assurance activities reqeired 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 meetin'gs of the PRC and th'e MSRC.

1. Records for Environmental Ouelmntka which are covered under the provisions of paragraph'6.14.

m. Records for the Radiological Environmental Monitoring Program.

n. Records of the service lives of all hydraulic and mechanical snubbers including the date at which the service lite commences and associated installation and maintenance records.

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 end shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 - Deleted .

Amendment No. 28, 0/ddt/ddfdd/IS/24/80, 53, 77, 98, 110 6-14

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