ML20136C528

Amend 77 to License DPR-54,revising Tech Specs to Define Surveillance Requirements for Installed Snubbers

ML20136C528
Person / Time
Site:	Rancho Seco
Issue date:	12/24/1985
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20136C517	List: ML20136C513 ML20136C528 ML20136C532 ML20136C554
References
TAC-43606, NUDOCS 8601030356
Download: ML20136C528 (17)

Text

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+ . . . . /s SACPAMENTO MUNICIDAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 77 License No. OPR-54 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for ame'ndment by Sacramento Municipal Utility Di:trict f the licensee) dated April 7,1981, as supolemented and revised by the licensee's letters of November 14, 1983, and-April 9, 1985, complies with the standards and requirements of the Atocic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application ,

the provisions of the Act, and the rules and 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 cenducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFP Part 51 of the Commission's regulations and all applicable requirements 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. OPR-54 is hereby amended to read as follows:

B601030356 e5122g ,

PDR ADOCK OSOoO P

PDR

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_2_

Technical Scacifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.777 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE flVCLEAR REGULATORY CO MISSION

// C & G ,v w John F. Stolz, Director -

PWR Project Directorate #6 Division of PWR Licensino-B

Attachment:

Changes to the Technical Specifications-Date of Issuance: December 24, 1985 i

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ATTAC4"ET:7 TO LICEr;SE AtiEMD>*Ei'T h0. 77 FACILITY OPERATING LICEFSE NO. OPR-54 DOCKET t:0. 50-312 Replace the following pages of the Appendix A Technical Specifications

~with the enclosed pages as indicated.

The revised pages are. identified by Amendment number and contain vertical lines indicating the area of change.

Remove

_ Insert ix fx 3-51 3-51

- * ~

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 a-47d 4-47d 6-14 4-47e 6-14 pp, -

.w-, _ y e .y- -- ---w ---- ,-r ,y -,,.

RAtJOHC CI*:0 U'!!T 1 TECHNICAL 5?!CIF ATIONS usT c .A2u!

_Ta bl e 2.3-1 Pace Reactor Protection System Trip Setting Limits 3.5.1-1 2-9 Instruments Operating Conditions

3. 6-1 3-27 Safety Features Containment Isolation Valves 3.12-1 3-40 Safety Related Hydraulic Snubbers 3-51a-o l 3.14.1 Fire Detection Instruments for Safety Systems 3-55 3.14.2 Inside Building Fire Hose Stations

, 3-57a 3.15-1 Radioactive Liquid Effluent Monitoring Instrumentation 3-61 3.16-1 Radioactive Gases Effluent Fbnitoring Instrumentation 3-64 3.22 1 Radiological Environmental Monitoring Program 3-E3 3.22-2 Reperting Levels for Radioactivity Concentrations in Environmental Samples 3-E5 4.1-1 Instrument Surveillance Requirements 4-3 4;1-2 Minimum Equipment Test Frequency' A-8 4.1-3' Minimum Sampling Frequency 4-9 4.2-1 Capsule Assembly Withdrawal E:hedule at Davis-Besse 1

. 4-1:b 4.10-1 Environmental Radiation Monitoring Program 4 42 4.10-2 Operational Environmental Radia?. ion Monitoring Progra= a-223 4.14-1 Designated Safety Related Hydraulic Snubbers Functionally 4-47d,e Tested .Only As Required By The Snubber Seal Replacement Program 4.14-1 Snubbers Accessible During Power Operations 4-47c

' 4.17-1 Minimum Number of Steam Generators to be Inspected During Inservice Inspection -

4-56 4.17-2A Steam Generator Tube Inspection 4-57 4.17-23 Steam Generator Tube Inspection (Specific limited Area) 4-57a 4.17-3

.0TSG Auxiliary Feedwater Header Surveillance l 4-57b, 4.19-1 4-57c I Radioactive Liquid Effluent Monitoring Instru: entation Sun tillance Requirements 4-64 4.20-1 l Radioactive Caseous Effluent 7:enitoring Instrumentation Surveillance Requirements

• 4-66

' Amendment No. 7$, $3, $$, SE, 7$, 77 ix

RAN;HO SECO UNIT 1 TECHNICAL SPECIF,lCATIONS Limiting Cenditions for Operation 3 12 SNUEEETS i

All snubbers listed in Table 3.12-1 shall be OPERABLE.

Acolicability Vnen the reacter sysee= is at ECT SHUTDOC?, ECT ST/.::DSY, ST.G27 er ?G*c:.R OFI?J.T*0N. During CO*.D SE'.~~DOZi and EIFTEI!NO only snubbers le:ated c systems required to be O? IRA 3LI for nuclear safe:y. l Action Vith 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 4.14.c on the supported comcenent or declare the supported system' inoperable and follow the appropriate specification statement for that system.

Bases Snubbers are designed to prevent unrestrained pipe motion uncer dynamic loads as might occur during an earthquake or severe transient, while allowing normal thermal motion during startup 'and shutdown. The conse-quence 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 cynamic loads.

It is therefore retuired tnat all snubbers required to protect ~ the primary coolant system or any other safety system or component be operable during reactor operation.

Amendment No. 9, 77 3-51 l

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PANCH3 SECO U?ifT 1 TECHNICAL SPECIFICATI0lis Limiting Conditit s fcr Operation TABLE 3.12-1  ;

SACETY RELATED HYDRAULIC SNUSSERS l List Snubber System Snubber Installed Accessible or ,

!!c. I.D. No. On, location and Elevation Inaccessible (A or 1) .

1 MS-20528-5W-1 MSS, TB, 13' A 2 MS-20521-SW-11 MSS, TB, 13' A 3 MS-20520-SW-3 MSS, TB, 13' A 4 MS-20521-SW-13 MSS, TB, 13' A  ;

E MS-20520-SW-5 MSS, RBY, 13' A 6 MS-20521-SW-14 MSS, RBY, 13' A  !

7 MS-20520-SW-13A MSS, RBY, 4' A

,8 MS-20520-SW-6 MSS, RBY, 36' A 9 MS-20526-SW-9 MSS, RBY., 36' A .,

. 10 9-SW-30709-3A MSS, TB, 20' A 11 9-SW-30708-4 MSS, TB, 29' A' 12 9-SW-30703-5A MSS, TB, 23' A .

13 9-SW-30709-4 MSS, TB, 23' A 14 9-SW-30709-3 MSS, TB,. 30' A i 15 5-SW-20530-7A MSS, RBY, 30' A  :

16. 5-SW-20529-3A MSS, TB, 39' A 17 5-SW-53520-3 HVS, RBY, 20' A 18 5-SW-32141-1A FWS, RBY, 20' A 19 5-SW-32141-2 FWS, RBY, 26'

• I 20 10-SW-20530-3A MSS, TB, 35' A  !

21 12-SW-20530-3A MSS, TB, 26' A 4 22 7-SW.32120-1B FWS, RBY, 14' A 23 7-SW-32120-1A FWS,'RBY, O' A 24 7-SW-32120-1C FWS, RBY, 2' A 25 MS-20550-SW-1 MSS, RBY, 16' A 26 MS-20558-SW-1 MSS, RBY, 17' A 27 MS-20532-SW-1 MSS, RBY, 15' A -

28 MS-20531-SW-1 MSS, RBY, 16' A 29 7-SW-32140-2 FWS, RBY, 16' A 30- 4-SW-20024-3A RCS, AB, -34' A 31 4-SW-26101-2 DHS, AB, -37' A 32 '4-SW-26101-6 DHS, AB, -37' A 33 4-SW-25023-5A SFC, AB, -36' A 34 4-SW-26101-SA DHS, AB, -39' A ,

35 4-SW-25023-8A SFC, AB, -37' A j Amendment No. 77 3-5'l a

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RANCH 3 SECO UHIT 1 TECHNICAL SPECIFICATI0HS Limiting Conc:itions for Operation t

TABLE 3.12-1 (Continued) l S.7ETY RELATED HYDRAULIC SNUBBERS t

, List Snubber System Snubber Installed Accessible or No, I.D. No.

On, Location and Elevation Inaccessible (A cr Il 36 4-SW-26100-3 DHS, AB, -37' A 37 4-SW-26100-1A DHS, AB, -37' A 3B 4-SW-26022-13A DHS, AB, -6' A 39 4-SW-26025-43 DHS, AB, -10' A 40 4-S'4-23620-3A SIM, AB, -7' A 41 4-SW-53520-3 HVS, AB, 23' A 42 4-SW-29101-1A CBS, AB, -37' A P5 1-SW-10-B&W-5 RCS, RBISS, 2' P6 I

1-SW-10-B&W-6 RCS, RBISS, 2' P7 I

1-SW-10-B&W-7 RCS, RBISS, 2' I 50 1-SW-20025-3 RCS,.RBISS', -2' 51 1-SW-20025-1A I

RCS, RBISS, -2' I 52 1-SW-26020-5A. DHS, RBOSS, -15' 53 I 1-SW-26524-4A CFS, RBISS, -15' 54 1-SW-50060-8A I

NSW, RBOSS, -2' I 55 1-SW-22000-9 PLS, RBOSS, -14'-

55 1-SW-26021-5A I

- DHS,'RBOSS, -15' I 57 l-SW-26021-7A DHS, RBOSS, -15' EB 1-SW-26021-11A I OHS, RBOSS, -15'- I 59 1-SW-50063-2A NSW, RBOSS, -B' I 60 1-SW-23B23-8 SIM, RBISS, 3' 61 1-SW-23620-15A I SIM, RBISS, 12' I-62 1-SW-23626-3A SIM,'RBISS, 4' 63 1-SW-29122-2SA I CBS, RBOSS, 38' I 64 1-SW-29125-7A CBS, RBOSS, 34 '

, I 65 1-SW-29125-7C CBS, RBOSS, 37' 66 MS-20523-SW-2 I MSS, RBOSS, 25' I 67 MS-20521-SW-17 MSS, RBOSS, 25' 68 .1-SW-29125-9A I CBS, RBOSS,.35' I 69 1-SW-50050-2A- t'SW, RBOSS, 36' I

~

70 MS-20520-SW-18 MSS,'RBOSS, 25' 71 MS-20522-SW-2 I

' MSS, RBOSS, 25' I 72 1-SW-50060-3A NSW, RBOSS, 36' I 73 1-SW-32140-4

' FWS, RBOSS, 3' I I 74 1-SW-32140-2 FWS, RBOSS, 7' I Amendment No. 77 3-51b

P.ANCHO SECO UNIT 1 TECHNICM. SPECIFICATI055 Limiting Conditions for Operation i

TABLE 3.12-1 (Continued)  !

SAFETY RELATED HYDRAULIC SHUEBERS .

8.ist Snubter System Snubber Installed Accessible or No. I.D. No. On, Location and Elevation Ina:cessible (A cr I)

5 1-SW-32141-4 FWS, RBOSS, 3' I 76 1-5W-32141-2 FWS, RBOSS, 7' I 77 1-SW-50053-2A NSW, RBOSS, -8' I

~ 5J-31520-7 FWS, RBISS, 30' I j

i-SW-31320-5 FWS, RBISS,.30' I j 1-SW-31821-7 FWS, RBISS, 30' I 1-SW-31821-8 FWS, RBISS, 30' I

'l-SW-22001-55 PLS, RBOSS, -19' I 1-SW-22001-56 PLS, RBOSS, -19' I 101 'M.5-20520-SW-19 FWS, RBISS, 30' I 102 MS-2' o21-5 20 FWS, RBISS, 30' I 103 MS-20521-SW-22 FWS, RBISS, 30' 104 I

MS-20520-SW-21 FWS, RBISS, 30' I 105 10-SW-20553-1A P,SS, TB, 26' A 105 5-SW-20529-1A MSS, TB, 35' A 107 5-SW-20529-4A MSS, RBY, 41' A 108 5-SW-20530-8 MSS, RBY, 28' A 109 7-SW-30800-6 MSS, RBY, 25' A 110 7-SW-30500-8 MSS, RBY, 25' A 111 7-SW-30500-12 MSS, RBY, 38' A 112 7-SW-30300-14 MSS, REY, 41' A 113 7-SW-30SO4-1 MSS, RBY, 28'. A 114 7-5W-30805-2 MSS, RBY, 28' A-115 5-SW-23803-4A PLS, TB, -9' A 116 4-SW-60014-4A RCD, TB, -30' A 117 1-SW-22000-12 PLS, RBOSS,.-19' 118 1-SW-22000-2A I

PLS, RBISS, -15' I 120 1-SW-21007-7 SIM, RBISS, -2' 121 I 1-SW-21022-5 RCS, RBISS, 0.5'

.122 I 1-5W-21005-6A SIM, RBISS, 3' I 123 1-SW-23525-1A SIM, RBISS, 5' 124 1-SW-21022-1 I

RCS, RBISS,11' I 125 1-SW-21021-3 .iCS, RBISS, 15

125 1-SW-23823-7A I

SIM, RBISS, -5' I  !

127 - 1-SW-21025-9A RCS, RBISS, -3' I ,

Amendment No. 77 3-51c l

4 RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditiens for 0,wrati n TABLE 3.12-1 (Continued) i SA.:ETY RELATED HYDRAULIC SNUESERS  ;

List Snubber System Snubber Installed i No. I.D. No. On, Location and Elevation Accessible or Ina tessible (A cr 5 128 1-SW-21005-8 RCS, RBISS, -2' I 129 1-SW-23822-7B SIM, RBISS, 8' -

130 1-SW-21028-2 RCS, RBISS,~16' 1

131 1-SW-25020-6A I DHS, R50SS, -16' I 132 1-SW-20052-12A SFC, R30SS, -14' ,

I  !

133 1-SW-25521-2A CFS, RBISS, -14'  !

134 1-SW-21025-6 I

'CCW, RBISS, -2' 135 1-SW-23823-13A I SIM, RBISS, 5' I 136 1-SW-21501-20 SIM, RBISS, 13' I 137 1-SW-21501-28_ SIM,.RBISS, 7' I 138 1-SW-30050-6A NSW, RBOSS, -5 '

ss-1 SS-1 I

-ss-2 RCS, RBISS, 31 '

55-2 RCS, RBISS, 31 '

I

-ss-3 55-3 I.

ss-4 RCS, RBISS, 31 '

55-4 I RCS, RBISS, 31 '

I

.ss-5 55-5 ss-6 RCS, RBISS, 31' SS-6 RCS, RBISS, 31' I ss-7 55-7 I ss-8 RCS, RBISS, 31' 55-8 RCS, RBISS, 31' I SS-9 55-9 I RCS, RBISS, 31' I

, ss-10 55-10 ss-11 RCS, RBISS, 31' 55-11 RCS, RBISS, 31' I

ss-12 55-12 I j ss-13 RCS, RSISS, 31' 55-13 I

ss-14 RCS, RBISS, 6' 55-14 RCS, RBISS, 6' I I

ss-15 55-15 ss-16 RCS, RBISSc 5' 55-16 RCS, RBISC o' I ss-17 55-17 I ss-18 RCS, RBISS, 6' 55-18 RCS, RBISS, 6' I ss-19 55-19 I RCS, !:BISS, 6' I

ss-20 55-20 ss-21 RCS, RBISS,-6' 55-21 .RCS, RBISS, E' I ,

ss-22 55-22 I ss RCS, RBISS, 6'  !

55-23 RCS, RSISS, 6' I i ss-24 55-24 I RCS, RSISS, 6' I

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Amendment No. 77 3-51d '

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS 4

Limiting Conditions for Operation Table 3.12-1 (continued)

SAFETY FILATED HYDRAULIC StGBBERS Snubbers may be added to safety related syste=s without prior License Amendment s j

to Table 3.12-1 provided that a revision to Table 3.12-1 is included with the next License Amendment request.

s Snubber Location Key  !

AB Auxiliary Building '

CBS Containment Building Spray System

. CCW Component Cooling Water CFS Core Flood System

- DHS Decay Heat System HVS PLS Heating /Ventila' ting / Air Conditioning System Purification and_Let-down System MSS Main Steam System NSW Nuclear Service Cooling Water RBISS RBOSS Reactor Building - Inside Secondary Shield RCD. -

Reactor Building - Outside Secondary' Shield Reactor Coolant Drain System RCS Reactor Coolant System RBY Reactor Building Yard SFC Spent Fuel Cooling System SIM TB Seal Injection. and Make-up System Turbine Building Fn'S Feedwater Amendment No. 77 3-51e l

-. - . = -_ - .. . .. . .

' RANCHO SECO U:;;T 1 TECENICAL SPECIFICATIONS Surveillance Standards ,

! 4.14 SNUBEIRS-Each snubber shall b'e d' emonstrated OPERABLE by perfor=ance of the following:

I

a. Visual Inspections i

The.first inservice visual inspection of snubbers shall be perfermed af ter four months but within 10 months of co=nencing P0k'ER OPERATION '

and shall include all snubbers listed in Table 3.12-1. If less than 4

two (2) snubbers are found inoperable during the first inservice i visual inspection, the second ins,ervicq, visual inspectica shall be i

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

, per Inspection Period Inspection Per#od*

0 18 months

• 25 1

l 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 may be categorized into two groups: Those accessible and those inaccessible during reactor operation.

independently in accordance with the above schedule.Each group may be inspected 4

l b. Visual Insoection Acceptance Criteria '

1

[

- Visual inspections shall verify (1)- that there are no visible indica-i tiens ,of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting s'tructure are secut.*, 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  !

i (1) the cause of the, rejection is clearly established and recedied

.: for that-particular snubber and for other snubbers that may be  !

generically susceptible; and (2) the affected snubber is functionally >

• The inspection interval shall not be' lengthened more than ene step at a ~

time' and Definition. section 1.9 does not apply. .

Amendment No. ), 77 f4-47 ,

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RANCP.0 SECO UNIT 1 i

TECHNICAL SPECIFICATIONS Surveillance Standards

' tested in the as found condition and deter =ined OPERA 3LE per Specifi-cation 4.14.d. However, when the fluid res'ervoir of a hydraulic 4

snubber is found to have the reservoir port uncovered, the snubber

.shall be determined inoper.ible and may be deter =ined OPERA 3LE via functional testing if-the test is started with the pisten in the as-found setting, extending the piston rod in the tension mode direction.

c. Functional Tests At i

least once per REFUILING INTERVAL, a representative sample (10%

of the total of each type of snubber io use in the plant) shall be functionally tested either in p15Ee or in.a bench' test. For each l

snubber that does not meet the functional test acceptance criteria of l'

Specification 4.14.d. an additional 10% of that type of snubber j.

shall be functionally tested.

The representative sample selected.for functional test sa=ple plans shall be randomly selected from the snubbers of each type and reviewed be-fore beginning the testing. Table 3.12-1 may be used as the basis of the sampling plan. Review shall ensure as.far as practicable that the selected snubbers are representative of the various configurations, operating

environments, and the range of size and capacity of snubbers of.each type.

Snubbers placed in the same location as snubbers which failed the previous functional test shall be retested at the time of the next functional test but shall not be included in the sample plan. If during the functional test additional sampling is required due to failure of only one type of snubber, the functional test results shall be revieued at that time to decer=ine if additional samples should be li=ited to the type of snubber which has failed the functional testing.

, Snubbers designated as being subject to functional testing only as required by the Snubber Seal Replacement Program are, listed in Table 4.14-1. If

- additional snubbers' must be tested due to the results of functional tests, the snubbers listed in Table 4.14-1 need not be included in the additional testing, unless some snubbers are suspected of possessing a failure mode caused by manufacturer or design deficiency.

In addition to t>e 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 snubber (if it is' repaired and installed in another position) and the spare snubber shall belretested.

These snubbers shall not be included in the random sa=ple and the results of these tests shall not be used to determine additional testing requirements.

Amendment No. ), 77 4 47,

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RAICHO SECO C;IT 1 s

TECH!ICAI. SPECIFICATIONS Surveillance Standards If any snubber selected fer functional testing either f:ils ** i lockup or fails to cove, i.e., frozen in place, the cause will be l

evaluated and if caused by manufacturer or ' design deficiency all snubbers of the same design subject to the same defect shall be

~

functionally tested. This testing requirement shall be independent 2 of the requirements stated above for snubbers not meeting the functional test acceptance criteria.

For the snubber (s) found inoperable, an engineering evaluatien shall be performed en the components which are supported by the snubberis}.

The purpose of this engineering evaluation shall be to deter =ine if the components supported by the snubber by the inoperability of the snubb'Er(s) I(.s) were. adversely affected in order to ensure that the i supported component remains capabl'e of meeting the designed service.

d.

Evdraulie Snubbers Functional Test Accentance 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 compression.

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, 1 the ability of the snubber to withstand load without I

displacement shall.be verified.

e. Snubber Seal Reelacement Program i

The seal service life of hydraulic snubbers shall be monitored te ensure that the service life is not exceeded between surveillance inspections. . The expected service life for the various seals, seal materials, and applications shall be determined and established based that on engineering infor=ation and the seals shall be replaced so the expected service life vill not be exceeded during a period when the snubber is required to be cperable. The seal replacements shall be documented and the documentation shall be retained in accordance with Specification 6.10.2.h.

All safety related snubbers are subject Approximately 20% of all safety related snubbers will undergo sealto the Seal R replacement during each refueling outa'ge. Credit taken for any snubbers rebuilt during the previous ~ fuel cycle.for seal replacemen Following seal replacement every snubber will be functionally tested.

The Functional Test Acceptance Criteria'(4.14d) shall be applicable to this testing. This testing will ensure that snubber is functionally tested as an integral portien of the sealevery safety'syste= hydra replacement program.

t In no case will snubber seal expected service life exceed ten fuel cycles .

Amendment No. /, 77 4-47b

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance. Standards Bases All snubbers are' required OPERAELE to ensure that i the structural integrity of the reactor cooiant system and all other safety related systems is maintained during ond following a seismic or other event initiating dyna =ic leads.

Snubbers excluded frem this inspection program are : hose installed on nensafe:y-related syst' ems and then only if : heir failure or failure of the system en which they are installed, would have no adverse effect on any safety-related system.

The vi'sualtoinspec:

pro:ection systems. ion frequency is based upon maintaining a constant . level-of snubber with the observed snubber failures and is determined by the number of i snubbers found during an inspection.

elapsed may be used as a new reference pointInspections performed before tha: interval has aver, to deter =ine the next inspection. How-time interval required inspectionhas elapsed (nominal time less 25~) may not be us interval.

tien interval will override the previous schedule.Any inspection whose results require a sher:e When tha: the cause aof the rejection of a snubber is clearly established and re=edied or f verified by inservice func:ional testing, thatsnubber and for any other snubber i

counced as inoperable. snubber may be exempted fre= being Generically susceptible snubbers are those which are of a cf :he' snubber by visual inspection, or are similarly located cspecifi exposed to the same environmen:a1 cendi icns such as temperature, radiation, and vibra:icn.

When a snubber is found inoperable, an engineering evaluation is performed , in addition to :he determination of the snub ~o'er mode of failure, in order to determine if any safety-related of the snubber. component or system has been adversely affected by the inoperabil The engineering evaluation shall determine whether or no: the snubber mode supported component of failure has imparted a significant effect or degrada: ion on the or system.

The requirement to monitor-the snubber maintenance reccrds is included to ensure that operating end the snubbers conditions. periodically undergo a performance evaluation in view of their ge a

tion of snubber service life.These records will provide the bases for future considera-snubber service life review'are notThe requirements for the maintenance 'of records and the intended to affect plant operation.

The snubbers listed in Table 4.14-1 are those snubbers other significant risks to personnel safety.

o the whic functional testing required for these snubbers is limited to tha: Based on these censideratiens necessary to assure opera:icn wi:hout exceeding the expec:ed service life or to address generic cencerns regarding operability of a particular'cype of snubber.

Amendment No. 7, 77 4_47, O

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Table 4.14-1 Limi:ing Conditions for Operacien DESICHATED SAFETY RELATED HYDRAULIC SNUBBERS FUICIONALLY TESTED ONLY AS REQUIRED 3Y TEE SNUB 3ER SEAL REPLACEMENT PROGRAM Snubber

, List No. I.D. No. Syste= Snubber Installed On, Location and Eleva:icn P-5 1-SW-10-B&W-5 P-6 RCS, RSISS, 2' 1-SW-10-35W-6 RCS, RBISS, 2' P-7 1-SW-10-B&W-7 53 RCS, R3ISS, 2' 1-SW-26524-4A CFS, RSISS, -15' 55 1-SW-22000-9 PLS, REOSS, -14' 111 7-SW-30800-12 MSS, REY, 38' 116 4-SW-60014-4A RCD, TB, -30' 117 1-SW-22000-12 PLS, RBOSS, -19' 122 1-SW-21006-6A SIM, RBISS, 3' 125 1-SW-21021-3 126 RCS, R3ISS, 15' 1-SW-23823-7A 130 SIM, R31SS, -5' 1-SW-21028-2 137 RCS, RBISS, 16' 1-SW-21501-28 SS-l' SS-1 SIM, RBISS, 7' SS-2 SS-2 RCS, REISS, 31' SS-3 SS-3 RCS, P3ISS, 31' 4

SS-4 SS-4 RCS, RSISS, 31' SS-5 55-5 RCS, P31SS, 31' i

SS-6 SS-6 RCS, P3ISS, 31' SS-7 SS-7 RCS,- RSISS, 31' SS-8 SS-8 RCS, RSISS, 31' SS-9 SS-9 RCS, P3ISS, 31' 55-10 SS-10 RCS, P3ISS, 31' SS-11 SS-11 RCS, RBISS, 31'

'SS-12 SS-12 RCS, P3ISS, 31' SS-13 SS-13 RCS, R3ISS, 31' SS-14 SS-14 RCS, P3ISS, 6' SS-15 SS-15 RCS, R3ISS, 6' 55-16 SS-16 RCS, RBISS, 6' SS-17~ SS-17 RCS, RBISS, 6' 55-18 SS-18

.RCS, R3ISS, 6'

'SS-19 SS-19 RCS, RBISS, 6' 55-20 SS-20 RCS, RBISS, 6' SS-21 SS-21 RCS, P3ISS, 6' -

55-22 SS-22 RCS, R3ISS, 6' SS-23 RCS, RBISS, 6' SS-23 SS-24 SS-24 RCS, P3ISS, 6' .

RCS, R31SS, 6' Amendment No ), 77 4-47d

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PE CHO SECO UNIT I TECHNICAL SPECIFICATIONS Li=iting Conditicos for Operation Table 4.14-1 (continued)

SNU3BER LOCATION IGY A3 AUXILIARY EUILDING CBS CONTAINMENT EUILDING SPRAY SYSTEM CCW COMPONENT COOLING WATER CFS CORE FLOOD SYSEM DHS DECAY HEAT SYS*EM FWS FEEDWATER SYSTEM HVS HEATING / VENTILATING / AIR CONDITIONING SYSTEM PLS PURIFICATION AND LETDOWN SYSTEM k

MSS MAIN STEAM SYSTEM NSW NUCLEAR SERVICE-COOLING UA~ER R3ISS REACTOR BUILDING - INSIDE SECONDARY SF.IELD R30SS REACTOR BUILDING - OUTSIDE SECONDARY SHIELD RCD REACTOR COOLANT DRAIN SYS~EM RCS REACTOR COOLANT SYSTEM REY FIACTOR BUILDING YARD SFC SPENT FUIL COOLING SYS EM SIM SEAL INJECTION AND MAREUP SYSTEM TB TUREINE BUILDING NOTE: i-List nu::ibers preceded by the letter "P" are associated with the pressuri:er.

Amendment No. 77 6-47e w - - , , -- - , -,,-,,--r -, -- ,

s-w A_ X*E ?L o :. CON 20' S b.

Records of acv and irradisted fuel inven:=g, fuci - - #- s and ass =hly burnap hi.st:rias.

c.

Records of far*ry radiation and conta=ina. ion st m.s, .

d.

Records of radia:ien a=posure fe: all .isiividuals enteri=:

radia:1:n ecstrol areas.

a.

Records of gaseous and liquid radios::ive material released to the envirnns.

f.

Records of transient or operational cycles for those fa *:7 compenests designed for a 11=ited nunbar of transients or cycles.

3 Records plas: of training opers:ing and qualifica inn for current me=hers of the staff.

h.

Records of in-service inspections peric=ed pursua t to these Tech =1 cal Specifica: ions.

1. Re=:rds of Quali:7 Assurance activi:les required by the QA w=-a-1.

j.

Records of reviews ~ perferned fer changes made to phocedures or equipme=t or revieva of tests and ==perime=ts pursuant to 10 CT1 50.59.

k. Records of meetings of the PRC and the 2GE::.

1.

Records for Environmental Qualifica:ict Ad.ch are covered under the provisions of paragraph ~6.14 m.

Records for Environmental Monitoring Progran, n.

J Records Table of the maintenance of all hydraulic snutbers listed in 3.12-1.

6.11 RA31CION FROTIL""!CN PRDCLtM Procedures for personnal radiation protection shall be prepared consista=t w1:h the requireme=:s of 10 CTR Part 20 and shall be approved, maintained 4

and adhered :s for all opera: ions involving personnel radiation a=posure.

6.12 - Deleted Amendment No. 2 C 6:14

" a. 34. '"/'"l^0 Amendment No. p . 77

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