ML20059G952

Amend 115 to License DPR-54,revising License Condition Re Fire Protection Plan,Adding Administrative Controls to Tech Specs in Support of Fire Protection Plan & Relocating Fire Protection Requirements to Fire Protection Plan

ML20059G952
Person / Time
Site:	Rancho Seco
Issue date:	09/10/1990
From:	Weiss S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20059G946	List: ML20059G942 ML20059G952 ML20059G962
References
NUDOCS 9009140072
Download: ML20059G952 (23)

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k UNITED STATES j

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NUCLEAR REGULATORY COMMISSION.

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SACRAMENTO MUNICIPAL UTILITY DISTRICT pdCKETNO.50-312 3

RANCHO SEC'J NUCLEAR GENERATING STATION i

AMENDMENT _TO FACILITY OPERATING LICENSE 4

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Amendment No,115 l

i License No. OPR-54 1.

The Nuclear Regulttory Comission (the Comission) has found that:

A.

The application for amendment by Sacramento. Municipal Utility District (the licensee), dated December 28, 1989, and supplemented

)

March.16, 1990, complies with the standards and requirements 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'o>erate in conformity with the ap)11 cation the provisions of tiv Act, and the regulations of tie Comission; i

C.

Thereisreasonableassurance(i)thattheactivitiesauthorized 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 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 CFR 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 Specifica-t tions as; indicated in the enclosure to this license amendment, and

>aragraph 2.C.(2) and 2.C.(4) of Facility Operating License No. DPR-54 are 1ereby amended to read as follows:

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4 2-t (2) Technical Specifications The Technical Specifications contained in Appendices A and B,.as revised through Amends. tnt No.115, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications.-

(4) The licensee shall implement and maintain in effect all provisions of the approved fire protection arogram, as described in the Fire Protection. Plan for Rancho Seco Veclear Generating Station, and as approved in the SER dated Septater 10,1990 subject to the following provision:

The licensee may make changes to the approved fire protection'

~i program without prior approval of the Consission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

I' 3.

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

FOR THE NUCLEAR REGULATORY COMMISSION has4J

=j= m Seymour H. Weiss, Director Non-Power Reactor, Decornissioning and Environmental Project Directorate Division of Reactor Projects - III, IV, Y and Special' Projects Office of Nuclear Reactor Regulation U

Attachment:

i Changes to the Technical Specifications Date of ~ !ssuance: Septater 10,1990 l

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i ATTACHMENT TO LICENSE AMENDMENT NO.115 FACILITY OPERATING LICENSE NO. DPR-54 DOCKET NO. 50-312 1

l Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and j

contain vertical lines indicating the area of change.

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INSERTION /REMOVALINSTRUCTIONS(cont.)

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Definitions 1.11 DELETED 1.12-STAGGERED TEST RASIS i

4 A STAGGERED TEST BA$!$ shall consist of:

a.'

A test schedule for n systems, subsystems, trains or designated components obtained by dividing the specified test-interval into n equal subintervals.

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The testing of one system, subsystem, train or designated

. components during each subinterval.

1.13 PROCESS CONTROL PROGRAM j

PROCES$CONTROLPROGRAM(PCP)-ThePROCESSC0kTROLPROGRAM contain the sampling, analysis, and formulation determination by

,which $0LIDIFICATION/DEMATERING of radioactive wastes-from.11guid.

systems is assured.

1.14 SOLIDIFICATION I

SOLIDIFICATION shall be the conversion-of radioactive wastes from-liquid systems to a homogeneous (uniformly dist-ibuted),

' monolithic, immobilized solid with definite volume and shape, i

1 bounded by a stable surface of distinct outline on all sides (free-standing).

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gip gg% 4 g, '. " RANCHO,$E M ' UNIT:1I y, g c;..y ,e.! % TECHNICAL SPECIFICATIONS; > , s x,w - s, ' Administrative Controls; pfl Y. w, ,j ".i [q FACILITYSTAFF. t xQj 16.2.2

The Facility organization'shall,be as shown in.the.USAR and:-

cw %r a. Each'on duty shift sh'all be composed _of at least the minimum 3 f, shift crew composition'shown in Table 6.2-1.; w, sf N b. At least one licensed Operator, shall be in the control room when-fuel.is in the reactor. 4 g s. c. . At least two licensed Operators, one of. whom shall-be: senior.. b + s, . licensed; shall be present in.the control room when the unit is; A in.other than' cold shutdown or. refueling. .4, j a d. An individual qualified Liniradiation protection practices and ~ proceduresLshall be~on; site when-fuel is-in'thd reactor. L.> e.- ~ LL CORE ALTERATIONS af ter the initial-fuel Ioading shall be~ -directly supervised by either a licensed Senior Reactor,0perator' @N or Senior.ReactorL0perator limited to Fuel Handling-who has no> a other concurrent responsibilit_ies during this operation. G f. DELETED L g. Administrative procedures shallibe developed and implemented to? l limit the working hours of. facility staff who perform safety-related functions; e.g., senior reactor operators,' m reactor operators, radiation protection personnel,-auxiliary-1 Q operators..and key maintenance personnel.-

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. RANCHO SECO UNIT 1..1 TECHNICAL SPECIFICATIONS-Administrative Controls ~- -3 m a

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3. m s 4 . 6.' 3 < = FACILITY STAFF'0UALIFICATIONS .J .l '6.3.1 Each1 member of the unit staff shallimeet or exceed the minimum - qualifications of ANSI N18.1-1971 for comparable positions, except -for-(1)-the Manaaer,' Radiation Protection who shall: meet or exceed-s. C-1the' qualifications of Regulatory _1 Guide 11.8, September 1975, and (2)- the Shift Technical Advisor who shall have a bachelor's degree or 7 equivalent in a scientific or engineering. discipline. The STA shall-

• y receive: specific' training,in.: plant design.and' response and analysis:

of the plant for. transients and accidents.-- . e. s "I 6.4 TRAINING ] 4 ?; O 64.1 ' A'retrainingand' replacement'Nainingprogramfor.theoperatingstaff: m sh'all:be maintained under the direction of;the Manager Training ,'U ~ and shall meet or exceed the requirements'and recommendations of c 'W ' ' Section 5.5 of ANSI.N18.1-1971=and Appendix;"A" of'10 CFR, Part 55.> W 1.- 6.4.2 ' DELETED.. 1 w :;. 6, f 6.5' REVIEW AND AUDIT ,n 'c w 6.5.1 PLANT REVIEW COMMITTEE (PRC)

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j, '_; s FUNCTION ga "j. ~6.5.1.1 The! Plant: Review Committee shall' function to advise the AGM, Nuclear - ,Y ', Power Production'and'tho' Management: Safety Review Committee on all ff$, matters:related toinuclear safety. .e COMPOSITION lu ~ ,7_ Of 6.5.1'.2: The Plant Review Committee shall be composed of a chairman, andLa minimum of six members.. i; _ M t is '4 W. 3., ,8, 7. 4. + .u ) i ;m LT s-m. i j,s ( Amendment No.14, 78, 24, 37, 82, 98,115 b f3 i>, 6-3 qjp 'N; ', p jn y L iM.

QQjll}u@y. #jl .RANCM0 SECO UNI 11 2~~ n2 1 l 4 + PM TECHNICALSPECIFICATIONSl t, j g !j ? Q b y W. l 4 Adainistrative Controls. Q@gg W X, Yh,Mhh RESPONSIBILITIES ~ (Continued)' e-g# (e[/']iy{, _g, A11 events requiring a Licensee Event ReportLas' defined by. ggg ~ 10CFR50.73 and NUPEG 1022 to. determine adequacy of corrective g 1 action and to detect any degrading trend.' W[ , i, [% -h. Special investigations and reports thereon.as requested by the AGM, Nuclear Power Production. ' [ hl .] ' Al3l[ i.- :The Plant Security-Plan and changes 1thereto. cm wy ev+ 1 b1 h 1.. The Emergency Plan and changes thereto.: a ' m" 7-a- -kL. Changes toLthe PROCESS CONTROL PROGRAM, the OFFSITE DOSE- . fi ,L g! $ L m O' - PROGRAM MANUAL'. (See Specifications 16.15:and 6.16.): ' j" CALCULATION MANUAL and the RADIOLOGICAL ENVIJt0NMENTAL MONITORING: qMw>' M,, @ l %~ .1. Ma or changes to the Radioactive Maste Treatment Systems' ' i $96W %e (L quid, Gaseous and-Solid), and al1<information required by-M tu Specification 6.17.- 1 j pb :. N Review of any accidental, unplanned,: or' uncontrolled: release of r W9 a ; m. !!jpM3 tradioactive' material-to the environs including the preparation 1 1 ' and. forwarding of resorts covering evaluation. recommendations,' hs p$"? and' disposition of tie corrective. action to prevent recurrence k l ~ and the forwarding of these reports to the Nuclear Plant Manager d * % '4 and to the L p mmO. MSRC.. j ws 4 -180 i n. The Fire Protection Plan and changes thereto, < AUTHORITY n '6.5.1.7 The' Plant Review Committee shall: 'l ~ jy .a. 'Recomend in writing to the AGM,' Nuclear Power Production c . approval-or disapproval of items considered under 6.5.1.6(a)- sy

through -

4 - (m) above. .y - b.~ Render;detirminations(inwritingwithregardto'whetherornot-j each item considered under 6.5.1.6(a)' through (e), and (1)' above ~ constitutes'an unreviewed, safety question-7 c.. Provide immediate written notification to the ChairmanLof the: Tm Management Safety Review Committee'of disagreement between the-PRC and the AGM, Nuclear Power Production; however, the AGM, g;* e Nuclear Power Production shall:have responsibility for: S resolution of such disagreements pursuant to 6.5.1.1 above. k# Amendment No. 24, 62,'63, 96, 98, 115 l s if '( @L ~ j s. bib i n d2Sh ?, ; l

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' RANCH 0 $ECO UNIT.11

~~ l 9 Q ,g,;yr.l + iTECHNICAL; SPECIFICATION $'. p . g +m h. P 5:. t.i . Adainistrative Controls-j ' - n 1 +r,; + ..p RESPONSIBILITIES.(Continued)' ' + ' 4 m 7.. i RECORDS ai 3&_ ^ y L6'.5d.8-Ricordsof.thePRC'activitiesshall'be' prepared,approvedan'd M, a : distributed as: indicated below:- .a. ' ' Minutes of-each.PRC meeting, including' appropriate - f' ' ' 7 " ? ' documentation of reviews encompassed by Specification: .6.5.I'.6e'and g, shall'be prepared, approved..and forwarded b to the AGM, Nuclear, Power Production and to the Chairman,

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. Management Safety ~ Review Committee within' fourteen (14) ' E days following each meeting. ) sa. pn (- '4 j e l

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.yp h. n, p 4 m=. n j\\;,- j' 4 i. ? r yh bd' U y .a Mt l .l r k.. ) 1 o oc , I ', ' i 4 )) . j. } ,j yq a 1m A t l. s 3? i s i:a u f 1 '? c f; 'n; I. L n qv, R run a j,n. 5 p qr Il o m I , 6): r

Arnendment NoE 24, 62, 63, 96, 98,115 w

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TECHNICAL'SPECIFICATIONSl u. y K g;~ ,a. Administrative Controls n~: + y k L 6' 7 : EAFETY LIMIT VIOLATION d l gn q-s ~'W~, l6.7.1l The folloiting actions sh' ll be taken in the event a Safety Limit.1:1 a 3 ^ violated:- m ia.J The proviitons of.10 CFR 50.36(c)(1)(1) and 10 CFR 50.72 shall be '1 complied with. g

• W b..

The NRC Operations Center shall.be notified by telephone as soon as A pssible and in all cases within'one hour. The AGM. Nuclear Power E,, Production and the Chairman of the MSRC shall be notified within 24-7e hours.- 9. .c. A' Safety Limit Violation Report'shall.be prepared. -The report shall, be. reviewed by'the PRC. This report shall;desc'.4he (1), applicable 1 " circumstances preceding the violation. (2) effectsiof the violation. .upon facility components, systems or structures, and (3) corrective CL action taken to prevent recurrence. d. The' Safety Limit Violation Report shall be submitted to the Connission, the MSRC, and the AGM. Nuclear Power Production, within-L 14 days of the violation.t g '6.8 PROCEDURES 'P. '6.8.1 (%' .Mritten procedures shall be established implemented and maintained covering the activities. referenced below-i. l

a.

The applicable procedures recossended in Appendix 'Aof Safety Guide 33. November 1972. l, b.' ' Refueling operations. L c.' Surveillance andttest activities of. safety related equipment, a d. Security Plan implementation., e.. -Emergency Plan implementation, 1 m f.- FIRE PROTECTION PROGRAM. implementation. 1_ g. PROCESS CONTROLiPROGRAM implementation. L*w h. OFFSITE 00$f CALCULATION MANUAL implementation.. N -1. RADIOLOGICAL ENVIRONMENTAL' MONITORING PROGRAM MANUAL implementation.- i . j.- Quality Assurance Program for Effluent Contro1~and Environmental 1;s Monitorinl1 using the guidance of ;tegulatory Guide 4.15. Revision 1, February'.979. gg m .6.8.2 'Each procedure of 6.8.1 above and changes thereto shall be reviewed j and approved as set forth in Specification 6.5.- G4 1 at o.s i e r i 'h-L lam dment No.-78, 24.'83. 87. 98, 98 ,115 6-11 1 k s; l$ i _[_ _ _._j__1

f(CNNICALl$P(CI?! CAT 10NS y j~. i,4, s p

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"V, Ad0ini.stratt've' Controle? -y T.n 'N, , g 3 g,,,,,,, x L'L 6' 9.5 4 " Special: reports shall be submitted toL the RegionaliAdministrator, _+., 1 l 7" ' . Region V Office, within-the time, period. specified for each report; o These reports-shall be submitted covering the activities identified -belowgcation::ursuant to the requirements of the applicable reference .specif ^ 7 t" a < A. A one-time only, " Narrative Summary.of Operatin'g Experience" will be ' submitted to cover the transition period (calendar' e f year 1g77), ~ l.?.' m.8. -A Reactor Building structural integrity report shall be. submitted within ninety-(90)- days. of-completion of each of- ,a~ the following tests covered by Technical Specification 4.4.2 ~ ,1 (the integrated leak rate test is covered in Technical' Specification 4.4.1.1). - i : 1 'I.- Annual Inspection M t.; Tendon Stress Surveillance. w7 3. End Anchorage Concrete Surveillance [< J 4; Liner Plate Surveillance C. In-Service Inspection Prograa. r ^ D.- InoperableAccidentMonitoringInstrumentationl 30: days: o, S (3.5.5)- E. DELETED g i t i F. Inoperable Emergency Control Room /TSC' Ventilation Room Fiiter Systes-f G. Radioactive Liquid Effluent Dose 30 days.(3.17.2f-o ' - C H. Noble Gas Limits 30' days (3.18.2) o4 -a 1. Radiciodine and Particulates. 30 days (3.18.3). s n .E L Amendment No. 80, 85, g7,115 6-12f k / \\ b h ' '3 ___.__i_m'--}}