ML20064B371

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Amends 47 & 10 to Licenses NPF-39 & NPF-85,respectively, Changing Administrative Controls Section 6.0 of Tech Specs, Including Addition of New Tech Spec Section 6.5.3 to Reflect Implementation of Station Qualified Reviewer Program
ML20064B371
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 10/04/1990
From: Butler W
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20064B372 List:
References
NUDOCS 9010160264
Download: ML20064B371 (31)
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l' 'i NUCLEAR REGULATORY COMMISSION l r, -e WASHING TON, D. C. 20555 - \\,,,/ PHILADELPHIA ELECTRIC COMPANY'

DOCKET NO.-50-352 LIMERICK GENERATING STATION,' UNIT?1 AMENDMENT TO FACILITY-OPERATING" LICENSE?

= Amendment: No. '47

License No. NPF-39 1.

The Nuclear Regulatory Commission (the Commission) has found'that A.~ The application for amendment by Philadelphia' Electric Company; (the licensee)-dated JulyJ 13; 1990,Ecomplies with the standards and requirements of the Atomic Energy Act of;1954,.as amended = (the Act), and the Connission's rules and regulations set forth. w* 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 Consnission; C. Thereisreasonable-assurance:(i)-thatthe;activitiesauthorizedby' ) this amendment can be conducted without endangering the-health andL ( 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 s 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. i 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. NPF-39-is!hereby amended to readLas' follows:: Technical Specifications-The Technical Specifications contained in Appendix A-and the: EnvironmentalLProtection Plan contained in Appendix B, as revised-through Amendment No. 47, are hereby incorporated into.this: license. Philadelphia Electric Company shall operate the facility in accordance with-the Technical Specifications and the Environmental Protection Plan. kRl0160264 90joo4 p ADOCK 05000352 :e PNU .. -. - -. ~ . -. z. u-,=. -

i p. .'r .s 1 - q ) 3. This, license' amendment is effective 90. days from datelof. issuance.. FOR THE NUCLEAR REGULATORY. COW.ISSION' 4 & i

Walter R.. Butler, Director Project Directorate I-2 Division of Reactor Projects --I/11-

Attachment:

Changes to. the-Technical' . Specifications.. t Date of Issuance:- October 4, 1990 i r ~ l 1 t 1 L. 1 M0'B'?h,ky PD1W$/t PDI-2/P OGC ' PDI-2/D' l RClark cpw . WButlerJ... t l i /90 ju/45/90 09/27/90 foL'/// /90 Q " r

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-[ 90 dayc fa m ] '3. - This license airendment is effectivegv'A date of issu ce, FOR THE NUCLEAR REGULATO COMMISSION i 4 f Walter R. Butler, Director-j Project Direc ate I-2 Division'of actorProjects.-.I/II .t i Attachment': Changes to the Technical Specifications Date of Issuance:- 1 6 'l l' g l e i e a.i,P OGC@< PDI-2/J PDI-2/D-

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j'- / ATTACHMENT TO LICENSE AMENDMENT NO. 47 FACILITY OPERATING LICENSE-NO.'NPF DOCKET NO. 50-352. i-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.. Overleaf-pages are I provided to maintain document-completeness.*' Remove Insert I xxvii-xxvii xxviii xxviii* 6-7 .6-7* 6 6-8 6-11 6-11* i 6-12 6-12 6-12a 6-13 13 6-14 6-14* 6-19 6-19 6-20 '6-20* -i w w

-i i 9 INDEX i ADMINISTRATIVE CONTROLS i E L SECTION PAGE. s i 15.5.2 NUCLEAR REVIEW BOARD (NRB)' 1 Function'...............................'..............." 6-9' .i Composition............................................ 6-9 Alternates.........................-.................... 6-10 Consultants............................................ '6-10 l ' Meeting Frequency........................................ 6 > 5 ~ Quorum..............................................-.... 6 10' Review.................................................. 6-10 l Audits.................................................- 6-11; j Records................................................ 6-12: 6.5.3 PROGRAM / PROCEDURE REVIEW AND APPR0 VAL................... 6-12' 6.6 REPORTABLE EVENT ACTI0N..................................... 6-12a' i 6.7 SAFETY LIMIT VIOLATION......................................- 6-12a I 6.8 ' PROCEDURES AND PR0 GRAMS................................'.....- 16-13~ 6.9 REPORTING REQUIREMENTS 9 6.9.1 ROUTINE REPORTS....................................... 6-15. L Startup Report......................................... 6 j Annual Reports........................................ 6-15 Monthly Operating Reports......... 6-16. Annual Radiological Environmental Operating-Report..... 6-16 Semiannual Radioactive Effluent Release Report......... 17' l CORE.0PERATING LIMITS REP 0RTS.....................-...... 6-18a l 6.9.2 SPECIAL REP 0RTS........................................ 6-18a 6.10 RECORD RETENTION........................................... 6-19 6.11-RADIATION PROTECTION PR0 GRAM............................... 6-20 l 6.12 HIGH RADIATION AREA........................................ 6-20 > LIMERICK - UNIT 1 xxvii Amendment No. 4&T,47 w n-.. _. -+ry n. -~-,..e ,.m.- ,+~,-v,4& cv a,, -y yw-m

l 4 4 . 1 INDEX ADMINIS'ina.. 6 LONTROLS SECTION PAGE' 6.13 PROCESS CONTROL PROGRAM (PCP).............................. 6-21 i 6.14 0FFSITE DOSE CALCULATION MANUAL (00CM)..................... 6-22 1 J 6.15 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS....... 6-22 l { 1 o j l l. LIMERICK - UNIT 1 xxvili .... ~ - - - - - - - - - + - - " - - ~

1 ADMINISTRATIVE CONTROLS '6.4~ TRAINING 3' -6.4.1 A; retraining and replacement training program for-the unit staff.shall be' maintained under the direction of' site training organization and shall meet or exceed the requirements of ANSI /ANS 3.1-1978 and 10 CFR Part 55 and the supple 4 a mental: requirements specified in Sections A'and C ofl Enclosure 1 of,the March 28,- [t 1980 NRC letter to-alll licensees, and shall include familiarization with-relevant-indust'ry operational experience. q 6.5 1 REVIEW AND AUDIT 6.5.1 -PLANT OPERATIONS REVIEW-COMMITTEE (PORC)' s FUNCTION 6.5.1.1 The PORC shall' function to advise the Plant Manager on all matters related to nuclear safety. COMPOSITION i D

6. 5.1. 2 The PORCshall be compose'd ofcthei Chairman:

Superintendent - Operations. Member.: Superintendent - Technical Member: -Superintendent _ Maintenance / Instrumentation' and Controls. Member: . Superintendent:. Plant Services Member: Assistant Superintendent;-l Operations Member: Regulatory Engineer Member: . Technical: Engineer Member: Shift Superintendent Member: Maintenance Engineer 1 ALTERNATES 6.5.1.3 All alternate members shal.lbe< appointed in writing by.the PORCI y Chairman to serve on a temporary basis;1however, no more than two alternates. 0 shall participate as voting members in PORC activities at any one. time, o 2 MEETING FREQUENCY 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairman or his' designated alternate. = QUORUM l 6.5.1.5 The quorum of the PORC necessar responsibility and authority provisions y for the performance of the PORC-of these Technical Specifications shall consist of the Chairman or his designated alternate and four members' including' alternates. l l j LIMERICK - UNIT 1 6-7 Amendment.No. 39, 33 '

ADMINISTRAT VE CONTROLS; RESPONSIBILITIES-T 6.5.1.6 The-PORC shall be responsible for:. Review of. (1) Administrative-Procedures and. changes thereto,-(2)inew' a.- programs or procedures required by Specification.6.8:and. requiring a 10 CFR 50.59 safety evaluation,_and.(3) proposed chan required by Specification 6.8 and requiring a ges'to programs or procedures 10 CFR'50.69 safety evaluation; b. Review of all proposed teststand experiments that affect nuclear. safety;; -Review'of,all proposed changes to Appendix A'. Technical:Specif.ications;! c. d. Review of'all proposed. changes _or modifications to unit; systems'or equipment that affect nuclear safety;; 'e. DELETED. f. Investigation of'all violations of=the Technical Specifications,_ including the preparation and forwarding of; reports covering evaluation and-recomendations to prevent recurrence, to-the Vice President, Limerick-GeneratingStation,PlantManager,and-tothe-NuclearReviewBoard;( g.- Review of all REPORTABLE EVENTS; h. Review of unit operations to detect potential hazards _to nuclear safety;- i. Performance of-special reviews, investigations, or. analyses-and reports thereon as requested by.the Vice President, Limerick Generating; Station,< Plant Manager or the Chairman of the. Nuclear Review Board;- j. Review of the Security Plan'and implementing-procedurestand submittal?of: recommended ~ changes to the_ Nuclear. Review Board; and k. Review of the Emergency Plan and; implementing. procedures and submittal of the recommended changes to the Nuclear Review BoardL 1. Reviewof'everyunplannedonsitereleaseof'radioactivematehia1Itothe-environs including the preparation'and forwarding ofc,reportsLcovering-evaluation, recomendations~ and disposition 'of: the corrective action to-prevent recurrence to the Vice President, Limerick Generating Station, Plant Manager, and to the Nuclear Review Board. ~ Review of changes to the PROCESS CONTROL PROGRAM, 0FFSITE DOSE CALCULATION m. MANUAL, and radwaste treatment systems.- 6.5.1.7 The PORC shall: s Recommend in writing to the' Plant Manager approval or:disapprovalnof items

a. -

considered under Specification 6.5.1'6a. through'd.: prior to their implementation, b. Render determinations in writing with' regard to.whether or not each item' .l-considered under Specification 6.5.1.6b. through'f. constitutes:an-unreviewed safety question. LIMERICK - UNIT 1 6-8 Amendment No. MI,47 i l

yj -1 ADMINISTRATIVE CONTROLS 1 ~ REVIEW (Continued)- All-recognized indications.of an unanticipated h, aspect of. design or operation of structures, sy; deficiency in some. g stems,- or components that could affect nuclear ' safety;' and i. Reports and meeting minutes'of the PORC. -AUDITS 1 '6.5.2.8 Audits of' unit activities shall be performed'under the cognizance ofi ~ he NRB. t These audits shall encompass:- The conformance of unit operation:to provisions contained within the a. Technical Specifications and applicable license conditions'at least' i once per 12. months; b. The performance, training andTqualifications of the entire unit staff i at least once per-12 months, 1 The-results of actions'taken.to correct deficiencies. occurring in c. unit equipment,' structures, sys.tems,;or method.of operation that? affect nuclear safety, at least once per 6: months; The performance of activities: required by the Operational Quality. d. Assurance' Program to meet:the criteria of Appendix ~B,110 CFR Part 50, at least once per 24-months; The Emergency Plan and implementing procedures'atileast_once per e. 12 months. f. TheSecurityPlanandimplementing' procedures-at'leaskonceper 12 months. g. Any.other area of' unit-operation considered appropriate by the NRB' or the Executive Vice President -' Nuclear. [ h. The Fire Protection Program and implementing procedures at'least once per 24 months. 1. An independent fire protection and loss prevention inspection'and' audit shall be performed at'least'once per 12 months utilizing either qualifled.offsite licensee personnel or_an outside fire protection _ firm, j. An inspection and audit of the fire protection and loss prevention program shall be performed by_an outside qualified fire consultant; at intervals no greater than 36 months. l LIMERICK - UNIT 1 6-11 Amendment No. g.35' OEC 191989-

' ADMINISTRATIVE; CONTROLS. I 1 i AUDITS (Continued)' I k.- The radiological' environmental. monitoring program and the results.thereof- { L at.least once.perc12 months. 1.. The OFFSITE-DOSE CALCULATION MANUAL and implementing procedures at least I once per 24 months-t The PROCESS CONTROL PROGRAM and implementing procedures at least once per m.. 24 months. The performance of activities required by the Quality Assurance Program n. to meet the criteria of Regulatory Guide 4.15, December.;1977 at least once per 12 months. i ' RECORDS q 6.5.2.9 Records of NRB activities shall be prepared,' approved.,and distr'ibuted,as indicated below: I . Minutes of each NRB meeting shall be prepared, approved iand forwarded:to-a. the Executive Vice President - Nuclear within 14-days following eachi meeting.- b. . Reports of reviews encompassed by Specification 6.5.2.7 shall be prepared, approved, and. forwarded to.the Executive Vice President - Nuclear.within 14 days following completion of the review.' o .i Audit reports encompassed by' Specification 6.5.2.8 shall be: forwarded to c. ~ the Corporate Officer (s)'and management positions' responsible for the - areas audited within 30 days after completion of the audit ~by the' l auditing organization. i 6.5.3 PROGRAM / PROCEDURE REVIEW AND APPROVAL J All programs and procedures required by Specification 6.8 shall be rev'iewed and fi approved as described below. 'i 6' 5.3.1. Each new program, procedure, or change.thereto shall: be' independently reviewed by a Station Qualified Reviewer (SQR) who is knowledgeable in'the functional, area affected but is not the individua1' preparer. The SQR may be from the same organization as the preparer. The SQR shall' render a determination in writing.of whether or not cross-disciplinary review of:a new'. program, procedure, or change thereto is necessary. If-necessary, such review shallybe performed by appropriate personnel. 6.5.3.2 Each new program, procedure, or change thereto shall be reviewed by the Superintendent designated by Administrative Procedures as the responsible- ~ Superintendent;for that program or procedure,'and the review shall'. include a determination of whether or not a 10 CF_R-50.59 safety evaluation is required..If a 10 CFR 50.59 safety evaluation.is not required, the new program, procedure,3orf change.-thereto shall be' approved by the responsible Superintendent:or the Plant 1 Manager prior to implementation.. Administrative Procedures shall be reviewed ~by PORC prior to approval. Administrative Procedures, Secur.ity Plan Implementing. -Procedures, and Emergency Plan Implementing Procedures-shall.be, approved by-the Plant Manager or his designated alternate in accordance with Specification ~6.1.1. LIMERICK - UNIT 1 6-12 Amendment No.,W, yy; 47 -i -+ ,,e s. -s t w+, - a

,z ., ADMINISTRATIVE CONTROLS-Ij q '6.5.3.3 If the responsible Superintendent determines.that a new program, 1 procedure, or change thereto requires a 10 CFR 50.59 safety evaluation, the responsible. Superintendent shall render a determination in. writing of whether or. not the'new program,-procedure, or change thereto question (USQ), and shall forward the new program,. involves an unreviewed safety 1 procedure, or change thereto .j with the associated safety evaluation to PORC for review. If an USQ is involved, i NRC approval is required by 10 CFR 50.59 prior to implementation of.the new j program,. procedure, or change. ~ 1 6.5.3.4 Personnel recommended to be SQRs shall be approved and designated-as-such. by the PORC Chairman. The responsible Superintendents shall-ensure.that a. sufficient complement of SQRs for their functional area is maintained.in accordance with Administrative, Procedures..The SQRs 'shall meet or exceed the' 1 qualifications described'in Section 4,4 of ANSI /ANS-3.1-1978. 6.5.3.5 Temporary procedure changes shall be reviewed and approved-in.accordance with Specification 6.B.3. 6.5.3.6 Records documenting the activities performed under Specifications 6.5.3.1 through 6.5.3.5 shall be maintained in accordance with Specification 6.10. a.6 REPORTABLE EVENT ACTION P 6.6.1 The following actions shall be:taken for REPORTABLE EVENTS:- The Commission shall be notified and a report submitted pursuant to the a. l requirements of Section 50.73 to 10 CFR Part 50, and b. Each REPORTABLE EVENT shall be reviewed by the PORC and submitted to the NRB, Plant Manager and the Vice President,~ Limerick Generating Station. 6.7 SAFETY LIMIT VIOLATION 6.7.1 I-The following actions shall be taken in the event a Safety Limit is violated: i The NRC Operations Center shall be notified by telephone as soon as a. possible and in all cases within 1 hour. The Vice President. Limerick-Generating Station, Plant Manager, and the NRB shall be notified within 24 hours. b. A Safety Limit Violation Report shall be prepared. The report shall. be - reviewed by the NRB. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of,the violation upon unit components, systems, or-structures. and-(3) corrective action taken to prevent recurrence, The Safety Limit Violation Report shall be submitted to the Commission, c. the NRB, Plant Manager, and the Vice President, Limerick Generating l Station, within the 14-days of.the violation. LIMERICK - UNIT'l 6-12a Amendment No. 47 i

@HINISTRATIVE CONTROLS 'SAFETYLIMITVIOLATION-(Continued)- t _ Critical operation of the unit shall not be resumed until authoriz$d by i d. the Commission.- j 6.8 PROCEDURES AND PROGRAMS .I 6.8.1 : Written procedures shall be established, implemented, and maintained covering the activities referenced below: The applicable procidures recomended in Appendix A of Regulatory-Guide a. 1.33 Revision 2, February 1978. i b. The applicable procedures required to implement the requirements of-1 HUREG-0737 and Supplement 1 to NUREG-0737. .)

c..

Refueling operations. d. Surveillance and test activities of safety-related equipment. e. Security Plan implementation. I f. Emergency Plan implementation. 1' g. Fire Protection Program implementation. h. PROCESS CONTROL PROGRAM implementation. 1. OFFSITE. DOSE CALCULATION MANUAL implementation. J. Quality Assurance _ Program for effluent and environmental monitoring,- using the guidance of Regulatory Guide 4.15. February-1979. 6.8.2 Each procedure of Specification 6.8.1, and changes thereto. and any other procedure or procedure change that the Plant ~ Manager determines to affect nuclear safety, shall be reviewed and approved in accordance with Specifications 6.5.1.6, 6.5.1.7 and/or 6.5.3, es appropriate, prior to implementation. Each procedure of-Specification 6.8.1 shall also be reviewed periodically'as set forth in Administrative Procedures. 6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made-i provided: The intent of the original procedure is not altered;' a. i b. The change is approved by two members of the unit management staff, at least one of whom holds a Senior Operator license on the unit affected; and '( 1_ l The change is documented, reviewed by an SQR in accordance with l c. j Specification 6.5.3.1, and approved by.either the Plant Manager or his i designated alternate in accordance with Specification'6.1.1,.or the L Superintendent designated by Administrative. Procedures as the responsible Superintendent for that procedure within 14 days of implementation. L l J LIMERICK - UNIT 1 6-13 Amendment No.,#,47 'l i

q ' ADMINISTRATIVE CONTROLS 1 3 - PROCEDURES AND PROGRAMS (Contin'ued). .h q 6.8.4 The following' programs shall-be establish'ed, implemented and maintained: De barv Coolant Sources Outside Containment a. t i A-orogram to reduce. leakage from those portions of systems ~outside; i containment that.could contain highly radioactive fluids curing a serious transient or accident-to-as low as practical levels, ~The-systems inc.lude the' core spray; high pressure coolant injection,.. reactor core isolation cool.ing, residual. heat removal, post-accident = sampling system, safeguard pipi_ng fill system,' control rod > drive; scram q discharge system, and containment air monitor systems'x - The program: sna11 include the.following, 1. Preventive maintenance and periodic visual inspection u requirements, and. l t 2.- . Integrated leak test requirements for each; system at refueling, c cycle: intervals.or less. ~ pi b. In-Plant Radiation Monitorina q t A program which will ensure the capability to accurately-determine: the airborne iodine, concentration in: vital areas under accident: conditions.~ 'This program shall include the following:. i j '1. . Training of personnel; 1 2. Procedures for. monitoring, and 3. Provisions for maintenance of_ sampling'and. analysis equipment. i c. Post-accident Samplino' 1 [j A program which will ensure the capabilityLto obtain and analyze reactor coolant, radioactive iodines and particulates:in plant gaseous offlu-ents, and containment atmosphere samples under accident conditions-The program shall include the following.. 'I 1. Training of personnel,- 2. ' Procedures for sampling and analysis, and I l 3. Provisions for maintenance of sampling and analysis equipment. .i q -] l LIMERICK - UNIT 1 6-14 - Amendment No. 29 3 JUN 2 21989 pvv r.-v,- .--w....-.,, -rd.--c.e 4 --~sr

ADMINISTRATIVE CONTROLS ~ 1 6.10 RECORD RETENTION 6.10.1' In addition to the applicable record-retention requirements of Title 10,. Code of Federal Regulations, the following records:shall be retained for at~least the 'nimum period indicated. 6.10.2 The following-records shall' be. retained for at'least -5 years:; Records and logs of unit operation covering time. interval at each: power a.- level. b. Records and logs of principal maintenance activities, inspections, repair, and replacementlof principal. items ofaequipment.related to~ nuclear safety.. c. All REPORTABLE EVENTS.' d. Records of surveillance. activities,11nspections, and? calibrations- ' required by these Technical Specifications., ~ i Records of changes made.to the programs and' procedures required'byf e. Specification 6.8. f. Records of radioactive shipments. ~ g. Records of sealed sourcecand fission.: detector leak tests.and-results. h. Records of annual: physical inventory of -alll sealed source material of record. 6.10.3 The following records shall be retained;for.thefduration:of the unit Operating License: 1 Records and drawing changes reflecting u' nit design modifications made to a. systems and equipment described in the Final Safety 1 Analysis Report. b. Records of new and irradiated-fuel' inventory, fuel transfers,1and assembly burnup histories. Records of. radiation exposure for all individuals entering radiation-c. 'I control areas. L l E L 4 i 'I 4 LIMERICK,- UNIT 1 6-19 Amendment No.47 .i

9 ADMINISTRATIVE CONTROLS RECORD RETENTION __(Continued) d. Records of gaseous'and liquid radioactive material released to the-

environs, Records of transient or operational cycles for those unit components e.

identified in Table 5.6.1-1. f.- Records of reactor tests and experiments. Records:of training and qualification for current members of the unit g. staff. Records of inservice inspections performed pursuant to these Technical-h. i Specifications, i. -Records of quality assurance activities required by the Operational: Quality Assurance Manual not-listed in'Section'6.10.'2. j. Records of-reviews performed for changes-made to procedures-or equip-- ment or reviews of' tests and experiments pursuant to_10 CFR 50.59.- '{ k, Records of meetings of the PORC and'the NRB., 1. Records of the service lives of all snubbers: including the datetat which the service 1.ife-commences and associated installation'and

j maintenance records.

'l 4 RecordsofanalysisrequiredbytheRadiolog'icalEnvironmentali d m. 1 ' Monitoring < Program that would permit evaluat_ ion"of the accuracy of. the-analysis at a later date. 'i 6.11 RADIATION PROTECTION PROGRAM. t 6.11.1-Procedures for personnel radiation protection shall1be prepared con. 'I sistent with the_ requirements-of 10 CFR Part 20 and shall tained, and adhered to for all operations involving person;be approved, main-nel radiation' exposure. y \\ 6.12 HIGH RADIATION AREA. i ) 6.12.1 In-lieu of the " control' device"1or-" alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20, each high radiation area in.which*the intensity-1 of radiation is greater than 100 mrem /h but-less than 1000 mrem /h shall be- = barricaded and conspicuously posted as'a high' radiation area.and entrance: y thereto shall be controlled by requiring issuance of?a Radiationz a Work Permit { (RWP)*. Any: individual.or group of_ individuals: permitted to enter such areas-shall be provided with or accompanied by one or more of the following: ' ]q A radiation monitoring device which continuously indicates.the-a. radiation dose-rate in the area. ' Health physics personnel or personnel escorted by health physics. personnel shall be exempt from the RWP issuance requirement during the performance of I their assigned radiation protection duties, provided they are otherwise following plant radiation protection procedures for entry into high radiation areas.

)

LIMERICK - UNIT 1 6-20s

3"4 e' UNITED STATES j g . 'j NUCLEAR REGULATORY COMMISSION M&HINGTON. D C. 206b5 g, / PHILADELPHIA ELECTRIC COMPANY DOCKET N0.-50-353 11MERICK GENERATING STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.10 License No. NPF-85 1. The Nuclear Regulatory Commissibn (the Commission) has found that A. -The application for amendment by Philadelphia Electric Company (the licensee) dated July 13 1990, complies with the standards and requirements of the AtomI'c Energy Act of 1954 as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter Il B. The facility will operate in conformity with the application the s provisions of the Act, and the rules and regulations of the Connist, ion; C. Thereisreasonableassurance(i)thattheactivitiesauthorizedby 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 Connission'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' ith 10 CFR Part 51 w of the Connission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the license is amended by changes to the Technical Specifications asindicatedintheattachmenttothislicenseamendment,andparagraph2.C.(2) of Facility Operating License No. NPF-85 is hereby amended to read as follows: Technical Specifications The Technical Specifications contained in Appen0ix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 10, are hereby incorporated into this license. Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection plan. e

e., i I -2 3. This license amendment is effective 90 days from date of issuance. FOR THE NUCLEAR REGULATORY COMMIS$10N /S/ Walter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects - 1/11

Attachment:

Changes to the Technical Specifications Date of Issuance: October 4, 1990 t I Phl PDI-2/ OGC PD1-2/D W 3. e'n PClark cpw WButler -{J/90 /d h3 /9 09 /27/90 [o//j./90 1 9 gee parviovi denewosner,s

2 3. This license amendeent-is effective as of its date of issua FOR THE NUCLEAR REGULATORY OMMISSION Walter R. Butler,.irector. Project Directo te 1 2 Division of R ctor Projects. 1/11

Attachment:

Changes.to the Technical Specifications Date of Issuance: l F A PDI-?/ OG g' PDI-2/D >4 RClark en WButler 9,. e,,e

= 2 3. This license amendment is effective 90 days from date of issuance. FOR THE NUCLEAR RECL'L ATORY COMMISSION j f/ ll u Walter R. Butler, Director. Project Directorate I-? Division of Peactor Projects,- I/II i

Attachment:

Changes to the Technical Specifications Date of Issuance: October 4, 1990 i h f a N t ~.

ATTACHMENT TO LICENSE AMENDPENT N0. 10 j FACILITY OPERATING LICENSE N0. NPF-85 DOCKET NO. 50-353 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. Overleaf.pages are i provided to maintain document completeness.* Remove Insert xxvii xxvii xxviii xxviii* 6-7 6-7* 6-8 6-8' 6-11 6-11* 6-12 6-12 6-12a 6-13 6-13 6-14 6-14* 6-19 6-19 6-20 6-20* ~$ 9 t t }

. = -. 1 l I i i INDEX I ADMINISTRATIVE CONTROLS ) SECTION PAGE l 6.5.2 NUCLEAR REVIEW BOARD (NRB) [ Function...........................................-... 6-9 ) Composition.......................................... 6-9 Alternates............................................. 6-10' Consn1tants............................................ 6-10 j Meeting Frequency...................................... 6-10 Quorum................................................. 6-10 Review................................................. 6-10 l Audits................................................. 6-11 Records................................................ 6-12 6.5.3 PROGRAM / PROCEDURE REVIEW AND APPR0 VAL.................. 6-12 I 6.6 REPORTABLE EVENT ACTI0N..................................... 6-12a

6. 7 SAFETY LIMIT VIOLATION.....................................

6-12a 6.8 PROCEDURES AND PR0GRANS..................................... 6-13 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS....................................... 6-15 Startup Report......................................... 6-15 Annual Reports........................................ 6 Monthly Operating Reports.............................. 6-16 Annual Radiological Environmental Operating Report..... 6-16 Semiannual Radioactive Effluent Release Report......... 6-17 CORE OPERATING LIMITS REP 0RT........................... 6-18a 6.9.2 SPECIAL REP 0RTS........................................ 6-18a .c 6.10 RECORD RETENTION........................................... 6-19 [ 6.11 RADIATION PROTECTION PR0 GRAM............................... 6-20 P 6.12 HIGH RADIATION AREA........................................ 6-20' 4 LIMERICK - UNIT 2 xxvii Amendment No.,NT 10 -w v.--- ,.-n, -sm-

i t h 19 9. ADMINISTRATIVE CONTROLS I 1 Helm M i i 1

6. 13 PROCESS CONTROL P W " (PCP)..............................

6-21 a i 6.14 0FFSITE 00$f CALCULATION RANUAL (" ")..................... 6-22 I i 6.1$ MAJOR CHANGES TO RA0!0 ACTIVE R$TE TREATMENT SYSTDe$.......6-22 1 1 J J i l J I ) ) ) i t a l t L j I t i -t i I e i 1 a i I t b 4 4 r LIE RICK - LallT 2 xxvii1 t f t ...'v. 's w :.;.- ,=,,,,..u.- -- t !'**

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i i ADMINISTRATIVE CONTROLS ,6. 4 TRAINING f 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the site Training organization and shall meet or exceed the requirements of ANSI /ANS 3;1-1978 and 10 CFR Part 55 and the i supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience, j 6.5 REVIEW AND AUDIT l 6.5.1 PLANT OPERATIONS REVIEW Com !TTEE (PORC) 3 FUNCTION 6.5.1.1 The PORC shall function to advise the Plant Manager on all matters related to nuclear safety. COMPOSITION 6.5.1.2 The PORC shall be composed of the. Chairman: Superintendent - Operations Member: Superintendent - Technical Member: Superintendent - Maintenance / Instrumentation and Controls Memoer: Superintendent - Plant Services 1 Member: Assistant Superintendent - Operations-l Member: Regulatory Engineer i Member: Technical Engineer l Member: Shift Superintendent Member: Maintenance Engineer. i i' ALTERNATES I 6.5.1.3 All alternate members shall be appointed in writing by the PORC l Chairman to serve on a temporary basis; however no more than two alternates shallparticipateasvotingmembersinPORCactivitiesatanyonetime, l l MEETING FREQUENCY r 6.5,1.4 The PORC shall meet at least once per calendar month and as-convened i by the PORC Chairman or his designated a,1 ternate.' QUORUM l 6.5.1.5 The quorum of the PORC necessary for the performance of the PORC l l responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and four members. including alternates. \\ LIMERICK - UNIT 2 6-7 . - -.. =. - -. - . =. -.

ADMINISVRATIVE CONTROLS l t RESPONSIBILITIES l 6.5.1.6 The PORC shall_be responsible for: l a. Review of (1) Administrative Procedures and changes thereto, (2) new programs or procedures, required by Specification 6.8 and, requiring a 10 CFR 50.59 safety evaluation, and (3) proposed changes to programs or procedures required by Specification 6.8 and requiring a 10 CFR 50.69 safety l evaluation; l b. Review of all proposed tests and experiments that affect nuclear safety; Review of all proposed changes to Appendix A Technical Specifications; j c. d. Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety; j e. DELETED. l f. Investigation of all violations of the Technical Specifications, including l the preparation and forwarding of. reports covering evaluation and j recomendations to prevent recurrence, to the Vice President, Limerick Generating Station, Plant Manager, and to the Nuclear Review Board' g. Review of all REPORTABLE EVENTS; h. Review of unit operations to detect potential hazards to nuclear: safety; i. Performance of special reviews, investigations, or' analyses and reports thereon as requested by the Vice President. Limerick Generating Station. { Plant Manager or the Chairman of the Nuclear Review Board, J. Review of the Security Plan and implementing procedures and submittal of 1 recomended changes to the Nuclear Review Board; and k. Review of the Emergency Plan and implementing procedures and submittal of. the recommended changes to the Nuclear _ Review Board. 1. Review of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence to the Vice President, Limerick Generating Station, Plant i Manager, and to the Nuclear Review Board, Review of changes to the PROCESS CONTROL PROGRAM, OFFSITE' DOSE CALCULATION m. MANUAL, and radwaste treatment systems. 6.5.1.7 The PORC shall: Recommend in writing to the Plant Manager approval or disapproval of items a. considered under Specification 6.5.1.6a. through d. prior to their 4 implementation. b. Render determinations in writing with regard to whether or not each item considered under Specification 6.5.1.6b. through f. constitutes an l unreviewed safety question, l LIMERICK - UNIT 2 6-8 Amendment No.-10 L .. _ _ -.. _., _. -.-.~

i ? ADMINISTRATIVE CONTROLS Rid.E (Continued) l \\ h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components j that could affect nuclear safety;-and i. Reports and meeting minutes of the PORC. .) I AUDITS 1 6.5.2.8 Audits of unit activities shall be performed under the cognizance of These audits shall encompass: the NRt. i The conformance of unit operation to provisions contained within the 4. i Technical Specifications and applicable license conditions at least i once per 12 months; l b.- The performance, training and qualifications of the entire unit staff l at least once per 12 months; i The results of actions taken to correct deficiencies occurring in c. i unit equipment, structures, systems, or method of operation that affect nuclear safety, at least once per 6 months; The performanc's of activities required by the'0perational Quality-i d. Assurance Program to meet the criteria of Appendix B, 10 CFR Part 4 50, at least once per 24 months; The Emergency Plan and implementing procedures at least once per e. 1 12 months. f. The Security Plan and implementing procedures at least once per 12 months. g. Any other area of unit operation considered appropriate by the NR8 or the Executive Vice President - Nuclear, i h. The Fire Protection Program and implementing procedures at least once per 24 months. 1. An independent fire protection and loss prevention inspection and audit shall be performed at least once per 12 months utilizing either j qualified offsite licensee personnel or an outside fire protection firm. j. An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater then 36 months. l LIMERICK - UNIT 2 6-11

__ _ __.. ~_. ADMINISTRATDE CONTROLS AUDITS (Continued) k. The radiological environmental monitoring program'and the results.thereof .l at least once per 12 months. 1 1. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least ) once per 24 months. The PROCESS CONTROL PROGRAM and implementing procedures'at least once per~ m. 24 months. .The performance of activities required by the Quality Assurance Program n. to meet the criteria of Regulatory Guide 4.15. December, 1977. at least 'i once per 12 months. t i RECORDS 1 /i 6.5.2.9 Records'of NRB activities shall b'e prepared. approved, and distributed as indicated below: 1 j a. Minutes of each NRB meeting shall be prepared, approved, and forwarded'to ) the Executive Vice President - Nuclear within 14 days following.each j meeting. t ) b. Reports of reviews encompassed by Specification 6.5.2.7 shall be. I prepared, approved, and forwarded to the Executive Vice President Nuclear within 14 days following completion of the review.: ) Audit reports encompassed by Specification 6.5.2.8 shall.be forwarded to c. i the Corporate Officer (s) and management positions responsible for-the areas audited.within 30 days after completion of the audit by the auditing organization. 6.5.3 PROGRAM / PROCEDURE REVIEW AND APPROVAL I All programs and procedures required by Specification 6.8 shall be reviewed and ] approved as described below. 6.5.3.1 Each new program, procedure, or change thereto shall be independently reviewed by a Station Qualified Reviewer (SQR) who is knowled functional area affected but is_not the individual preparer. geable in the The SQR may be from 1 the same organization as the preparer. The SQR shall render a' determination in writing of whether or not cross-disciplinary review of a new program, procedure, or change thereto is necessary. If necessary, such review shall be performed by appropriate personnel. 6.5.3.2 Each new program, procedure..or change.thereto shall-be reviewed by the Superintendent designated by Administrative Procedures as the responsible Superintendent for.that program or procedure. and the review shall. include =a j determination of whether or not a 10 CFR 50.59 safety evaluation is required. If a 10 CFR 50.59 safety evaluation is not required, the new program, procedure, or change thereto shall be approved by the responsible Superintendent or the Plant Manager prior to implementation. Administrative Procedures shall be reviewed by~ PORC prior to approval. Administrative Procedures, Security Plan Implementing Procedures, and Emergency Plan Implementing Procedures shall be approved by the Plant Manager or his designated alternate in accordance with Specification 6.1.1. LIMERICK - UNIT 2 6-12 ' Amendment Ho. 10 ~

d' ADMINISTRATIVE CONTROLS i i t i 6.5.3.3 If the responsible Superintendent determines that a new program,-procedure, change thereto requires a 10 CFR 50.59 safety evaluation, the responsible i Superintendent shall render a determination in writing of whether or not.the new program, procedure, or change thereto involves an unreviewed safety question (USQ) and shall forward the new program, procedure, or change thereto with the associated safety evaluation to PORC for review. If an USQ is involved. NRC appiun1 is required by 10 CFR 50.59 prior to implementation of the new program, procedure, or

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I 6.5.3.4 Personnel recommended to be SQRs shall be approved and designated as such by the PORC Chairman. The responsible Superintendents shall ensure that.a sufficient complement of SQRs for their functional area is maintained in accordance with. 1 Administrative Procedures. The SQRs shall meet or exceed the qualifications t described in Section 4.4 of ANSI /ANS 3.1-1978. 6.5.3.5 Temporary procedure changes shall be reviewed and approved in accordance l with Specification 6.8.3. h 6.5.3.6 Records documenting the activities performed under Specifications 6.5.3.1 through 6.5.3.5 shall be maintained in accordance with Specification 6.10. 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS: I The Commission shall be notified and a report submitted pursuant to the a. requirements of Section 50.73 to 10 CFR Part 50, and-b. Each REPORTABLE EVENT shall be reviewed by the PORC and submitted to the NRB, Plant Manager and the Vice President. Limerick Generating Station. 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated: i The NRC Operations Center shall be notified by telephone as soon as possible l a. and in all cases within 1 hour. The Vice President Limerick Generating Station, Plant Manager, and the NRB shall be notified within 24 hours. b. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the NRB. This report shall describe (1) applicable. circumstances preceding the violation, (2) effects of the violation upon unitcomponents, systems,orstructures,and(3)correctiveactiontakento prevent recurrence, l The Safety Limit Violation Report shall be submitted to the Connission, the c. NRB, Plant Manager, and the Vice President, Limerick Generating Station, within the 14 days of the violation. i i i \\ LIMERICK - UNIT 2 6-12a Amendment No.10 { .i

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I f.DMINISTRATIVECONTROLS 'AFETYLIMITVIOLATION(Continued) S d. Critical operation of the unit shall not be resumed until authorized by the Commission. 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced:below; The applicable procedures recommended in Appendix A of Regulatory Guide a. 1.33. Revision 2. February 1978. b. The applicable procedures requirec a implement the requirements of' NUREG-0737 and Supplement 1 to NUREG-0737. i c. Refueling operations. i I d._ Surveillance and test activities of safety-related equipment. e e. Security Plan implementation, f. Emergency Plan implementation. g. Fire Protection Program implementation, b. PROCESS CONTROL PROGRAM implementation. i. OFFSITE DOSE CALCULATION MANUAL implementation, j. Quality Assurance Program for effluent and environmental monitoring, using the guidance of Regulatory Guide 4.15 February 1979. 6.8.2 Each procedure of Specification 6.8.1, and changes thereto, and any other procedure or procedure change that the Plant Manager deterrines to affect nuclear 6.5.1.7 and/or 6.5.3, as appropriate. prior to implementation.' safety Specification 6.8.1 shall also be reviewed periodically as set forth inEach procedure of. Administrative-Procedures, 6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made j provided: The intent of the original procedure is not altered; a. b. The change is approved by two members of the unit management staff, at least one of whom holds a Senior Operator license on the unit affected;' and I The change is documented, reviewed by an SQR in accordance with c. Specification 6.5.3.1, and approved by either the Plant Manager or his designated alternate in accordance with Specification'6.1.1, or the Superintencent for that procedure within 14 days of imple LIMERICK - UNIT 2 6 13-Amendment No.10 ,b

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 6.8.4 The following programs shall.be establishea, implemented, and maintained: a. Primary Coolant Sources outside Containment A program to reduce leakage'from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the core spray, high pressure coolant injec'. ion, reactor core. isolation cooling, residual heat removal, post-sccident sampling system, safeguard piping fill system,, control rod drive scram discharge system, and containment air monitor systems. The propan shall include the following: 1 1. Preventive maintenance and periodic visual inspection requirements, and 2. Integrated' leak test requirements for each system at refueling i cycle intervals or less. ~ b. In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine i the airborne ibdine concentration in vital areas under accident conditions. This program shall include the following: I' 1. Training of personnel, 2. Procedures for monitoring, and 3. Provisionsformaintenanceofsamplingandanalysisequipment, ~ c. Post-accident Samplino A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous efflu-ents, and containment atmosphere samples under accident conditions. The program shall include the-following: 1. Training of personnel, 2. Procedures for sampling and analysis, and 3. Provisions for maintenance of sampling and analysis equipment. 1 LIMERICK - UNIT 2 6-14

1 i ADMINISTRATIVE CONTROLS-i 6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10,: Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated. i I 6.10.2 The following records shall be retained for at least 5 years: i Records and logs of unit operation covering time. interval at each power i a. level. l b. Records and logs of. principal maintenance activities, inspections., repair, and replacement of principal items of equipment related to nuclear safety. c. All REPORTABLE EVENTS. t d. Records of surveillance activities, inspections, and calibrations required by these Technical Specifications, Records of changes made to the programs and procedures required by e. i Specification 6.8. f. Records of radioactive shipments. g. Records of sealed source and fission detector leak tests and results. h. Records of annual physical inventory of all sealed source material of record. 6.10.3 The following records shall be retained for the duration of the unit Operating License: Records and drawing changes reflecting unit design modifications made to a. systems and equipment described in the.'inal Safety Analysis Report. Records of new and irradiated fuel inventory' fuel transfers, and b. assembly burnup histories. Records of radiation exposure for all individuals entering radiation c. control areas, l l 1 LIMERICK - UNIT 2 6-19 Amendment No'.10

j. ADMINISTRATIVE CONTROLS l i RECORD RETEh10N (Continued) Records of gaseous and liquid radioactive material released to the j environs. e. Records of transient or operational cycles for those unit components identified in Table 5.6.1-1. i f. Records of reactor. tests and experiments. g. Records of training and qualification for current members of the unit staff. 1 h. Records of inservice inspections performed pursuant to these Technical Specifications. 1. Records of quality assurance activities required by the' Operational Quality Assurance Manual not listed in Section 6.10.2. j. Records of reviews performed for changes made to procedures or equip-ment or reviews of tests and experiments' pursuant to 10 CFR 50.59. i k. Records of meetings of the PORC and the NRB. 1. Records of the service lives of all snubbers including the date at which the service life commences and associated installation and 1 maintenance records. I \\ a m. Records of ana. lysis required by the Radiological Environmental l Monitoring Program that would permit evaluation of the accuracy of the analysis at a later date. 6.11 RADIATION PROTECTION PROGRAM o I 6.11.1 Procedures for personnel radiation protection shall be prepared con - sistent with the requirements of 10 CFR Part 20 and shall be approved, ma*In-tained, and adhered to for all operations involving personnel radiation j exposure. l 6.12 HIGH RADIATION AREA l 6.12.1 In lieu of the " control device" or "alare signal". required by paragraph 20.203(c)(2) of 10 CFR ' art 20, each high radiation area in which the intensity of radiation is greater '.han 100 mren/h but less than 1000 mrom/h shall be barricaded and conspicuously posted as a high radiation area and entrance i thereto shall'be controlled by requiring issuance of a Radiation Work Permit l (RWP)*. Any individual or roup of individuals permitted to enter such areas i shall be provided with or accompanied by one-or more of the following: i , s. A radiation monitor!ng device which continuously indicates the i radiation dose rate in'the area. L

  • Health physics personnel or personnel escorted by health physics personnel shall be exempt from the RWP issuance requirement during.the performance of their assigned radiation protection duties, provided they are otherwise following plant radiation protection procedures for entry into high radiation areas.

LIMERICK - UNIT 2 6-20 J .}}

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