ML20148S471

Amend 24 to License DPR-54,revising Administrative Controls Portion of Tech Specs in Response to 780221 Application. Reflects Revised Facility Organizaion Structure & Clarified Review Requirements for Security & Emergency Plans

ML20148S471
Person / Time
Site:	Rancho Seco
Issue date:	11/14/1978
From:	Reid R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20148S465	List: ML20148S471 ML20148S527
References
NUDOCS 7812010347
Download: ML20148S471 (19)

Text

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[em asog% UNITEO ST ATES

.l' ' 't NUCLEAR REGULATORY COMMISSION

$' M $ WASHINGTON, D. C. 20556 t /

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SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SEC0 NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amndment No. 24 License No. DPR-54

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

A. The application for amendment by Tacramento Municipal Utility District (the licensee) dated February 21, 1978, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter 1; B. The facility will operate in conformity with the application, J the provisions of the Act, and the rules and regulations of '

the Commission; l 4

C. There is reasonable assurance (1) 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 conducted in compliance with the Comission'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; I and E. The issuence of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable nequirements have been satisfied.

i 7812018347

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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 i

No. DPR-54 is hereby amended to read as;follows:

i (2)- Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 24, 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 the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMIS$10N <

( Robert W. Reid,/)-fChief

(

Operating Reactors Branch #4 Division of Operating Reactors Attachnent: )

Changes to the Technical Specifications Date of Issuance: November 14, 1978 1

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ATTACHMENT TO LICENSE AMENDMENT NO. 24 FACILITY OPERATING LICENSE NO. DPR-54 p0CKETNO.50-312 Revise Appendix A as follows:

Remove Pages Insert Pages 6-1 6-1 Figure 6.2-2 Figure 6.2-2 6-3 6-3 6-4 6-4 6-5 6-5 6-7 6-7

6-10 6-10 6-11 6-11 Revise Appendix B as follows

Remove Pages Insert Pages 41 41 42 42 j 1

43 43 l 44 44 4 47 47 48 48 49 49 50 50 Changes on the revised pages are shown by marginal lines.

Pages 41, 47 and 50 are unchanged and are provided for convenience only.

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I 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Manager of Nuclear Operations shall be responsible for the management of the overall facility and the Plant Suoer-intendent shall be responsible to him for the operation and maintenance of the plant. They shall delegate in writing the succession to their responsibilitv durina their absences.

6.2 ORGANIZATION i

0FFSITF l 6.2.1 The offsite organization for facility management and technical support shall be as shown on figure 6.2-1.

FACILITY STAFF l I

6.2.2 The Facility organization shall be as shown on Figure 6.2-2 and:

a. Each on duty shif t shall be comoosed of at least the minimum shift crew composition shown in Table 6.2-1, 1

b. At ' east one licensed Goerator shall be in the control room 1 when fuel is in the reactor, c, At least two licensed Operators shall be present in the control room during reactor start-uo, scheduled reactor shutdown and during recovery from reactor trips,

d. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor,

e. ALL CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a licensed Seninr Reactor Operator or Senior Reactor Ooerator limited tt Fuel Handling who has no other concurrent responsibilities during this operation.

f. A Fire Brigade of 3 members shall be maintained on the site rt all times. This excludes 2 members of'the minimum shift crew necessary for ' safe shutdown of the plant and any personnel required for other essential functions during a fire emergency.

Amendnent No. ,)d( 24 6-1 9

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MANACER OF

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• • l NUC L E AR CPEPAT I ONS PLANT

• TECHNICAL

• ADMINISTRATIVE ENGINEERING AND*

v SUPERINTENDENT ASSI5 TANT $TAFF QUALilY CONTROL SUPERVISOR

,a CHEMICAL & RADI AT ION

• OPERATIONS MINT E NANC E*

SUPERVISCR SUPE RVISOR l $UPE RVISOR (SL)

CHEMISTRY & PADI ATION SHIFT ELECTRIC AL. INSTRUMENT, PERSONNE L SUPERVISOR (SL) MECHANICAL MAINTENANCE FERSONNEL I I SR. P0.!ER PLANT

• QUALITY ENGINEER CONTROL NUCLEAR / MECHANICAL PERSONNEL SENIOR CONTROL ROOM GPERATORS (SL)

CONTF.0L ROOM OPE FATO RS (L)

AUXILIARY OPE PATO RS a

SL - Senior Operator License L - Operator License sa Fesponsible for Fire Frctectia,  !

rrogran '

EQUIPMEhT

• Routine F.coor t ing Fe:;ui re en ts l ATTENDENTS on Personnel changes RANCHO SECO UNIT I Figure 6.2-2

Sc.Itt; S M CtritATI.P.3 FLANT CRCAN!!ATt0*i * '~

Amendment No, ,%

A"tt!! !STRATIVE CONTROLS . . . . . - . . _ _ _

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FAC i t I TY STAFF OljM. l f l C A1 ID F.

6.3 m i. n i n e:

6.3.1 theb membe r o f t he c'n .rh t i ng s t: f i s h a l l i .r.c t or exc.ntd th:

qu0lifications cf ".M31 t 8,1 - l C / l for c> p;rnble positions.

'i h e Cherd enl-Md i atica P.upen ]: o r ch all 1.. ':t. ore /tnd 6.3.2 tb rninJ..c :ow.lificitt w of imt Guice 1.0 Sept.c.t m 1575.

6 . l: TRA'NINC.

6.1.1 1 A retraining and rel '. int i r a i n i r.. progrin for the eper: ting sta f f sha l l be ma i n t.; in .o encH:i th.; dirr.. tion of tha Trc.inin1 Superviser nr.d sh:.li a or excw: the rc:mi rerents u d recorn ar.d -

tions of Section 5.5 of AN::1 Ul b .1-1971 cad Ap;cnd i x "A" of 10 G'n '

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6. li . 2 A t rc i n i ng p' r ': r4:: t for th<f F i r, F r i t;3dc shc l l be imjintaincd under the dircction of inc 2"fct. te.n :tinn and thall coet or cycaed the requiremant- of 'ettien 27 ci t ha. f?FP A Coc'c - 19/5. ceccpt rcfreshes cla stoco training th: 11 be on c quartcrly rchecule.

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1 6.5.1 N 1'lT "!N I f.\! C 3.T 1 T~ " E :PRC) l FL'N:.7 rH

6,3,},1 The Plant Review Committee shall function to advise the Manager of Nuclear Operations on all matters related to nuclear safety.

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6. 5.1. : The Plant Review Cenaittee shall be ccaposed of the:

i C ha i rrea n : Techoical As::i stant th. ber: Operations supervisor

! : v.b a r -

Engineering and Quality Control Supervisor.

M mhar idaintenance Surcrvisor J

Menber: Chemical and Radiatiun Superviser Other members as the Manager of Nuclear Operations may appoint

from time to time.

J Amendment No. , ,24 6-3

ADMINISTRATIVE CONTROLS ALTERtlATES_  !

6.5.1.3 Alternate chairman or members shall be aopointed in writing by the I Manager of tiuclear Operations to serve on a temporary basis; however, l

no more than two alternates shall participate in PRC activities at any one time.

MEETING FREQUENCY

6.5.1.4 The PRC shall meet at least once per calendar month and as convened by the PRC Chairman.

i i OUORU'1 6.5.1.5 A Quorum of the PRC shall consist of the Chairman and two members l including alternates. .

1 RESPONSIBILITIES i

6.5.1.6 The Plant Review Committee shall be responsible for:

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a. Review of 1) all procedures reouired bv Specification 6.8 and changes thereto, 2) any other prooosed procedures or changes thereto ,as determined by the Manager of fluclear Ooerations to affect nuclear safety.

b. Review of all proposed tests and experiments that affect nuclear safety, i

c. Review of all proposed changes to the Technical Specifications.

j d. Review of all pronosed changes or modifications to plant systems

] or eauipment that affect nuclear safety, i

e. Investigation of all violations of the Technical Specifications and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence to the Plant Suoerintendent, ilanager of Nuclear Operations and to the Chairman of the Management Safetv Review Committee.

f. . Review of facility operations to detect potential safety hazards.

9 Performance of special reviews and investigations and reports thereon as reauested by the Chairman of the flanagement Safety Review Committee.

6-4 Amendment No.24

ADMIflISTRATIVE CONTROLS __._.

RESPONSIBILITIES (Continued)

h. Review of the Plant Security. Plan and implementing proceduzca and shall submit recor: unended changes to the Plan to t he Cho i t uu.. y of the Management Safety Review Committee.

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i. Review of the Emergency Plan and implementing procedures and i shall submit recommended changes to the Chairman of the ,

l Management Safety Review Committee. '

AUTHORITY 6.5.1.7 The Plant Review Committee shall: 1 l

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a. Recommend to the Plant Superintendent written approval or ,

disapproval of items considered under 6.5.1.6(a) through (d) l above,

b. Render determinations in writing with regard to whether or i not each item considered under 6.5.1.6(a) through (e) above constitutes an enreviewed safety question. i

c. Provide immediate written notification to the Chairman of the Management Safety Review Committee of disagreement between the PRC and the Manager of Nuclear Operations or the Plant Superintendent; however, the fianager of Nuclear Operations shall have responsibility for resolution of such disagreements ,

pursuant to 6.5.1.1 above. l RECORDS 6.5.1.8 The Plant Review Committee shall maintain written ninutes of each meeting and copies shall be provided to the Plant Superintendent,

^1anager of Nuclear Operations and the Chairman of the fianagement Safety Review Committee.

Amendment No. 2fi 6-5

d ADMINISTRATIV_E CONTROLS COMPOSITION 6.5.2.2. The MSRC shall be composed of the:

Assistant General Manager and Chief Engineer - Chairman Technical Assistant - Secretary Manager, Engineering Department Assistant General Manager, Operations Manager, Nuclear Operations Supervising Nuclear Engineer Manager, Generation Engineering Quality Assurance Director Quality Assurance Engineer Plant Superintendent ALTERNATES 6.5.2.3 Alternate Chairman or members shall be appointed in writing by the MSRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate in MSRC activities at any one time.

CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the MSRC Chairman to provide expert advice to the MSRC.

MEETIN,G FRE00ENCY 6.5.2.5 The tiSRC shall meet at least once oer calendar quarter during the initial year of facility coeration following fuel loading and at least once per six months thereafter.

OUORUM 6.5.2.6 A nuorum of MSRC shall consist of the Chairman or his designated alternate and a majority of the !1SRC members including alternates, No more than a minority of the quorum shall have line responsibility for operation of the facility.

Amendment No. 24 6-7 1 . , .

. . j ADMINISTRATIVE CONTROLS RECORDS 6.5.2.10 Records cf MSRC activities sht11 be prenared, approved, and distributed as indicated below:

a. Minutes of each MSRC meeting shall be prepared, approved and forwarded to the General Manager within 14 days  :

following each meeting.

b. Reports of reviews encompassed by Section 6.5.2.7 e, f, g and h above, shall be prepared, approved and forwarded to l

the General Manager within 14 days following completion of the review. i

c. Audit reports encomoassed by Section 6.5.2.8 above, shall be forwarded to the General Manager and to the management i positions resconsible for the areas audited within 30 davs j i

after completion of the audit.

6.6 REPORTABLE OCCURRENCE ACTION l 6.6.1 The following actions shall be taken in the event of a REPORTABLE OCCURRENCE:

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a. The Commission shall be notified and/or a report submitted pursuant to the reauirements of Specification 6.9.

b. Each Reportable Occurrence shall be reviewed bv the PRC and the renort shall be submitted to the MSRC, Manager of Nuclear Operations and the Plant Superintendent prior to its submittal to the Commission, l

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l Amendcent No. 24 6-10 9

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ADMINISTRATIVE CONTROLS 1

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The provisions of 10 CFR 50.36 (c) (1) (1) shall be complied with immediately.

b. The Safety Limit violation shall be reported to the Plant Super-intendent, the Manager of Nuclear Operations, the Chairman of the HSRC and to the Commission immediately.

c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PRC. This report shall describe (l) applicable circumstances preceding the violation, (2) e f fects of the violation upon fac i l i ty componen ts , sys tems or s t ruc tures ,

and (3) corrective action taken to prevent recurrence.

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d. The Safety Limit Violation Report shall be submitted to the Commission, the MSRC, the Manager of Nuclear Operations and the

} Plant Superintendent within 10 days of the violation.

l 6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November 1972.

b. Refueling operations.

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! c. Surveillance and test activities of safety related equipnent.

! d. Security Plan i mp l enen t a t i on .

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] e. Emergency Plan implementation, 4

f. Fire Protection Procedures implementation.

6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the PRC. Those matters pertaining to items 6.8.la, b and c, above shall be approved by the Plant Superin-tendent prior to implementation and reviewed periodically as set forth in each document. The manager of Nuclear Operations shall also approve Security Plan and Emergency Plan implementing procedures.

6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

a. The intent of the original procedure is not al tered.

AmendmentNo.f,2.k 6-11

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RANClio Sl'C0 UNIT 1 FIGURE 4-1

Sampic Collection ENVIRONMCNTAL TECllNICAL SPECIFICATIONS Location Stations

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.j 11 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility, A. The Nuclear Plant Superintendent is responsible for the operation of the facility and to assure that the facility operates within the limits set forth in the environmental technical specifications.

B. In all matters pertaining to nuclear operation of the facility and to the environmental technical specifications, the Plant Superintendent shall report to, and consult the Manager of Nuclear Operations.

C. The Plant Chemical and Radiation Supervisor is responsibic for maintaining the environmental monitoring program. There will be a semiannual audit of specific phases of the program by the Quality Assurance Group which will report their findings directly to the Assistant General Manager and Chief

Engineer. All audit results will be recorded in the records of the Management Safety Review Committee.

5.2 organization The organization charts are shown in Figures 5-1 and 5-2. The functional organization with respect to environmental matters is shown in cross-hatch. This involves reporting from the Chemical Radiation Supervisor to the Plant Superintendent. The

, Technical Assistant remains as an independent review and audit authority to monitor compliance with these Technical Specifications.

5.3 Review and Audit Committees for review and audit of plant operation are described in Section 6.5 of the Safety Technical Specifications.

s In addition to the responsibilities specified in Safety Technical

' Specifications, the Committees shall have the following responsibilities concerning the environmental impact of the plant.

A. Plant Review Committee (PRC)

1. Coordination of environmental technical specification development with the safety technical specifications to avoid conflicts and maintain consistency.

Amendnent No. 24

2. Review proposed onsite tests and experiments and results thereof, when such tests have environmental significance.

3. Review proposed changes to the environmental technical specifications.

4. Review written orocedures, as described in 5.5, and proposed changes thereto which affect the plant's environmental impact.

5. Investigation of all renorted instances of violations of environmental technical specifications. Where investi-gation indicates, evaluation and formulation of recom-mendations to prevent recurrence.

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6. Review results of the environmental monitoring programs prior to their submittal in each Annual Environmental fionitoring Reoort. See Section 5.6.1.

B. flanagement Safetv Review Committee (f1SRC) 1 Preparation of the proposed environmental technical speci fications .

2. Review proposed changes to the environmental technical specifications and the evaluated impact of the change, l

1 3. Review proposed changes or modifications to plant svstems or eouipment which would affect the plant's environmental impact and the evaluated impact of the changes.

4. Conduct periodic audits of plant operations.

5. Review all reported environmental specification violations.

5./ Action to be Taken in Event of Violation of an Environmental Fratection I.imi t.

5 . 4 .1 Remedial action as permitted by the Technical Specification shall be taken until the specification can be met.

5.4.2 A violation of these Technical Specifications shall be reported immediately to the Plant Superintendent and Manager of fluclear j

Ope ra tions . At a formal meeting of the Plant Review Committee, the Plant Superintendent or the Chemical and Radiation Supervisor shall report the technical aspects of the violation.

Amendment flo. [, 24' l I

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5:4.3 The chairman of the Plant Review Committee shall prepare a detailed evaluation report outlinina the events leading to the violation along with suagestions to prevent or reduce the probability of recurrence. This report shall be completed within one week of the occurrence. The evaluation report will be distributed to the Plant Superintendent, flanaaer of Nuclear Operations and to the Chairman of the Management Safetv Review Committee.

5.5 _P,,roce du re_s 5.5.1 Detailed written procedures, including aoolicable check lists and instructions, will be prepared and adhered to for all activities involved in carrying out the environmental technical specifica-tions . Procedures will include sampling and analvsis, instrument calibration, and actions to be taken when limits are approached or exceeded. Testina frequency of associated alarms will be included. The' frequencies will be determined from experience or from manufacturer's technical manuals.

5.5.2 In addition to the orocedures specified in Section 5.5.1, the l plant Process Standards will include provisions to ensure the plant and all its systems and components are operated in compliance with the environmental protection limits established ~

t in Section 2 of these ertvironmental technical specifications.

5.5.3 All procedures described above, and all changes thereto will be reviewed by the Plant Review Committee and aporoved by the Plant Superintendent prior to implementation. The procedures will be reviewed periodically thereafter. Temporary changes to orocedures which do not change the intent of the original procedure may be ]

! made, provided such changes are approved by two members of the Plant management staff. Such changes will be documented, l

b.> Plant Reoorting Recuirements c

5.6.1 Routine Reoorts A. Annual Environmental Ooerating Report Part A- Nonradioloqical Reoort. A report on the environmental

, surveillance programs for the previous 12 months of ooeration shall be submitted to the Director of the NRC Reaional Office (with a coov to the Director, Office of Muclear iteactor Regula-tion) as a separate document within 90 davs after January 1 of each year. The period of the first report shall begin with the date of initial criticality. The report shall include summaries, interpretations, and statistical evaluation of the results of the nonradiological environmental surveillance activities (Section 3) and the environmental monitorina nroarams reouired by the limiting conditions for operation (Section 2) for the report period, including a comparison with preoperational studies, operational controls (as aporopriate) and previous environmental surveillance reports and an assessment'of the observed impacts of AmendmentNo.[2fi

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A. Records and drawing changes reflecting plant design modifications made to cystems and equipment as described in Section 5.6.3.

l B. Records of environmental monitoring data.  ;

i 5.7.2 All other recordn,and logs relating to the environmental technical j specifications will be retained for five years. ,

5.8 Special Requirements Tabic 5-1 lists the typical amounts of chemicalo that will be dis- )

charged from the station. The list includes those chemicals which  !

are purchased and used in plant processes, and B and Zn , which are concentrated by the cooling towers from naturally occurring impurities in raw water, and which have specific waste discharge limits. The quantities actually discharged will be determined on an inventory basis as recorded in the warehouse chemical log book or from calculation of total discharge water and chemical analysis of the  ;

These quantitics shall be included in the Semiannual effluent.

Operating Reports (Section 5.6.1) if they appreciably exceed those

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in Table 5-1. ,

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GENERAL i,iii,,,,,,,,,,,,, ,

MANAGER /

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f ASSISTANT d GENERAL MANAGiR s AND CHIEF ENGINEER s s

MANAGE ME NT SAFETY REVIEW COMMITTEE

) s rv.nabER MANAGER ,, ,, f ENGINEERING NUCLEAR OPERATIONS PLANT SUPERINTENDENT CHEMICAL AND RADIATION SUPERVISOR

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PLANT REVIEW  !

COMMITTEE

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ENVI.RONMENTAL FIGURE 5-1 TECNillCAL SPECIFICATIONS i

MANAGEMENT OFGAN120 : il RANCHO SECO UNIT i  !

! i knendment No. 24 i

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MA*iACE R OF

• NUCLEAR OPE FAT IONS

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TECHNICAL

• ADMIN I ST F.AT i k E ENGINEERitiG AhD* PLANT *

$UPER!fiTENDENT ASSISTANT ST/*FF QUALITY C04TP.0L '

SUP E RVI SOR Y

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CHEMICAL f, RADI ATION6 OPERATIONS MAINTENANCE

• SUPERVISOR SUPERVISOR (SL) SUPERVISOR

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CHEMISTRY f, RADI AT ION SHIFT ELECTRICAL, INSTPUMENT, PE R50 TINEL SUPERVISOR (SL) MECHANICAL MAINTENANCE PE R50t:NEL I I SR. POWEF PLANT *' QUALITY I EN0(NEER CONTROL f;UCLCAR/ MECHANICAL PERSONt.EL SENIOR CCNTROL ROOM OPERATORS (SL)

CONTROL RCOM OPE PATO RS (L)

AUXILI ARY OPE RAT ORS

" SL - Senior Operator License i L - Operator License E Q'JIPt ENT

• Routine Reporting Pequiremnts ATTEhCEN15 on Fersonnel changes RANCll0 SECO UNIT 1 Figurc 5-2 E!W1RO:: "'::TAL TECHNICAL SPECIFICATIONS l'I.!dT 011CANIZATIO:; Ci:.ii'T Amendment No.2f+ 49 l

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TABLC 5-1 NON-RADIDACTIVE CHD11CALS AND ELEMENTS TYPICALLY RELEASED BY RANCHO SECO UNIT 1 IN THE EFFLUENT DISCHARGE Average Chemical or Acount Per Annual Conc.

Elenent Year (1bs) (ng/2) i Use and Frequency of Discharge Sodiu -(Nai 1.45 x 105 39 Regenerant of ion exchanger resin as sodium hydroxide.

Discharged inte rmi tten tly.

1 Svifate (50u) 1.6 x 106 431 Sulfuric acid injection into cooling tower water to reduce alkalinity and regenerant of ion exchanger i resin. ' Discharged continuously Am.cnia (NH3 ) 5. 2 x 10 14 i

$ Regeneraut of ion exchanger resin as ammonium hydroxide i

and pH adjustnent for steam generator feedwater.

Discharged intermittently.

Chlorine (Ct2) <750 <0.2 Biocide to remove aquatic grostiis in cooling water systems. Injected to cooling towers at %200 lbs. per day. Mainly consumed prior to discharge.

Alun [ Ay (30u) 3] 4.0 x 10" 1.7At Coagulant for water treatuent system. Discharged intermittently.

Boren (B) .%2 x 103 NO.6 Cooling tower concentration of naturally occurring B in raw water. Continuously di.scharged. No release of B used in plant processes.

Zinc (7.n) N1 x 103 NO.3 Cooling tcwer concentration of naturally occurring Zn 1

in raw water. Continuously discharged.

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, Hydruine (N2 11a) Negligibic Negligible Used for oxygen scavenging of secondary feedwater system. Consumed in process except during shutdcun periods.

H'- --ms',---~-meme _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ __ _ _ _ _ , ___ ___