ML20236Q940

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Proposed Tech Spec Pages 6-1,6-2,6-3,6-4,6-6,6-7,6-8,6-9, 6-11,6-12 & 6-13,changing Licensee Onsite & Offsite Organization
ML20236Q940
Person / Time
Site: Limerick 
Issue date: 11/18/1987
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20236Q898 List:
References
NUDOCS 8711200372
Download: ML20236Q940 (14)
v • d • e


Text

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N T N E RO I E Y R V C + = OS R E E R SVI A W . D E N + = E O S N E A I R P H N N RRV E N T N T I E EERE P O NO N GT EEEP A I I IT R TE NN NNPU T E AD EIA GG US= T R I I L E T N M NN S= O A E P S E S N H T N T R EE T D U S C R= S ST N ON E S RST I E= E N N NI I E O NAR TA OTSCE O O N I I O TE AT I T LI I NF D T T I S P R S G CUMSI F A S ASU ESN ASEYG A I TI I O TSS PSE EEHHNT T Z T P SA OA R RRCPES I IN E R A R E E G A N H I V R C G E O N W L E O N A H O N S T I L O R N A I O C T O O I R A T R I F Z A T T I O T N A C N R R I T S O Z E E A I RC N A O I P P R C G E ST I E A S R G I N O E S ED G V O N E PRY NN R A L D A D RL OOH I A NROO T P G A 2 O C E H 5R I T C LEO TR RTA T N N B3D E N N. S ATS AT ONR HS E I O T H O RN TAE TI I N O CNI I I VEOALPLM ETI i0 I CT 1 S O N NRRPCRP OAE C A g0 N EA E H EE O E EH N N 73 TZ O I L C PP T P T S YHC AE N D G N EUULN O N R NM T A BL O TSSOA A ARR EU E ]O N G TI A I RT T SLOO S T T TTTTS NI t I I TR E R 3 S O 1 I FFFNISASXNN INT O S I I I O HHHOSLSUEE A S 0D E P P SSSCAPAASS MI 0A R O D 2 N 2 P R E 2 1 PS 6 1R E O N 7D S H E P mO E 9PP L T O R I O R N U T R I MP G A E T I T G SC N T O E F S I NN O S R N H F O G L OA C IX T I N E T N U T + .D N I D D AE D S EI S T E A N S E R T = N YN V N G R AS E H E I R A L O OS L S TI E C C PA E N EOI N OM E N NTMN N S EA EA I A S CRV O N O NLNTR I I R C E C OAANE G. T TTTS I T RFI RM H = G NNNL G EA S RE A G S N R I CNOS EI C EEEO N CT UICI K TI E I N DDDR E N N CE I AN EC TGN FI C G R H ND NAN lUI EEE N E NM S LO T N NNN T R T* AE P EN E R A E N CI A T A A E L TI R R EU T AN LUL O TTTO R E P E N I LTI T R OTM A POP MT INNNC E OE TR TA A S MI R M C I I EI PE NT N L*R RRR NG PN I CN N 1 E E TTTNTTT TT D I NUI EEE A S NI O U O I TRG G P NNNONNNGNN PPP NG G N MIN O NI F I A E S T NEA U EEEI EEENEE T UUU AN N O I HIT D EGN N T DDDADDDIT SSST E Y S ET DD I T RR I CSB D DAA A R NNNTNNN RNN R A L*OO SEOO

Page 1 of 2 1 \\ _y ~ 4_ Appendix A List of Proposed Change's Propos'ed Changes Affected Pages Change the title Vice President-6-9 Electric Production to Senior 6-11 Vice President, Nuclear 6-12 Change the title Vice President-6-1 j Electric Production to Vice President, 6-12 Limerick Generating Station 6-13 Addition of title Vice President, 6-8 ) Limerick Generating Station Change the title Station Superintendent 6-1 ) to Plant Manager 6-2 j 6-7 6-8 6-9 { r Change title of Engineer-In-6-6 Charge Nuclear Safety Section to General Manager Nuclear' Ouality Assurance Change the title Engineer-In-Charge 6-6 Nuclear Safety Section to Manager Independent Safety. Engineering -Addition of the title Plant Manager 6-8 6-9 6-12 6-13 -{ l Change the title Superintendent-6-8 . Nuclear Generation Division to 6-9 Vice President Linerick Generating 6-11 ] Station Change the title of Superintendent, 6-7 Nuclear Training Section to Superintendent-Training 1 ] Page-2 of 2- -i 1 Appendix A List of Proposed Changes 1 Proposed Changes Affected Pages Deletion of the titles Superintendent-6-2 Maintenance Division and Engineer-In-Charge, Station Testing. Addition of the titles Superintendent-Plant Services,' Superintendent-Maintenance / Instrument and Controls, Superintendent-Modifications, and Superintendent-Technical. Deletion ofLthe titles Station Superintendent, 6-7 Engineer-0perations. Senior Health Physicist, Reactor Engineer, and I & C Engineer Addition of the titles Superintendent-0perations, Superintendent-Technical, Superintendent-Maintenance / Instrument and Controls Superintendent-Plant Services, and Assistant Superintendent-0perations i I } l [, 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence. 6.1.2 The Shift Supervisor, or during his absence from the control room, a designated individual shall be responsible for the control room command function. A management directive to this effect, signed by the Vice President, Limerick Generating Station shall be reissued to all station personnel on an annual basis, i 6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for unit management and technical support shall be as shown on Figure 6.2.1-1. UNIT STAFF 6.2.2 The onsite organization shall be as shown on Figure 6.2.2-1 and: a. Each on duty shif t shall be composed of at least the minimum shift crew composition shown in Table 6.2.2-1; b. At least one licensed Operator shall be in the control room when fuel is in the reactor, In addition, while the unit is in OPERATIONAL CONDITION 1, 2, or 3, at least one licensed Senior Operator shall be in the control room; c. A Health Physics Technician

  • shall be on site when fuel is in the reactor; l

1 d. ALL CORE ALTERATIONS shall be observed and directly supervised by either l a licensed Senior Operator or licensed Senior Operator Limited to Fuel l Handling who has no other concurrent responsibilities during this operation; e. A site fire brigade of at least five members shall be maintained on site at all times *, The fire brigade shall not include the Shift Superintendent, the Shift Technical Advisor, nor the two other members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency; and

  • The Health Physics Technician and fire brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours, in order to accommodate unexpected absence, provided immediate action is taken to fill the required positions.

LIMERICK - UNIT 1 6-1

j ADMINISTRATIVE CONTROLS 4 UNIT STAFF (continued) I f. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions (e.g., licensed Senior Operators, licensed Operators, health physics, auxiliary operators, and key maintenance personnel). Adequate shift coverage shall be maintained without routine heavy use of l overtime. The objective shall be to have operating personnel work a j normal 8-hour day, 40-hour week while the unit is operating. However, in the event that unforeseen problems require substantial amounts of overtime to the used, or during extended periods of shutdown for refueling, major maintenance, or major unit modifications, on a temporary basis the following guidelines shall be followed: 1. An individual should not be permitted to work more than 16 hours straight, excluding shift turnover time. 2. An individual should not be permitted to work more than 16 hours in any 24-hour period, nor more than 24 hours in any 48-hour period, nor more than 72 hours in any 7-day period, all excluding shift turnover time. j 3. A break of at least 8 hours should be allowed between work periods, including shift turnover time. 4. Except during extended shutdown periods, the use of overtime should j be considered on an individual basis and not for the entire staff on j a shift. Any deviation from the above guidelines shall be authorized by the Plant Manager or the Superintendent Operations, (for operating personnel) or j the Superintendent-Maintenance / Instrumentation and Controls or (for key maintenance and instrument and control personnel), or the Superintendent-f Plant Services (for chemistry and health physics personnel) or the Superintendent-Technical (for technical personnel), or the Superintendent-Modifications (for construction personnel) or their ) designee or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Plant Manager, or the appropriate superintendents or their designees to assure that excessive hours have not been assigned. Routine deviation from the above j guidelines is not authorized. LIMERICK - UNIT 1 6-2

AUN R MQA L A L ALP E R 8A N A NAP M U AUU LRU U A AAS O M O MOS ^^ A I RES - L N S G ELA = L NC' ~ EU GN T N G G T 2 E N G N N b D RI N RI RT .S E AR RRI ER EC TG I M S EAR GE GE SL T E GEE AE AJ ^ EE E G N LE R ALE NN NO R I l CN A OT A P NCN AI AR UI AUI MG MP N C P NG MNG N A U - H E E M S N N YC C E E N I V AN PO MI OT CA T Z N G CI E RR R RR RR S EA T E EA N EA N' D R GE N G G E I GEI N E N I I A AL A A L ALM RA S C I E NCA N N C NC D I TG - E I A R R V AUM A A U AU A L R C MN M M N E R P R T MN CR U EO D C E T N E E S L S R C N I C ET R A F I E O OF _ F D V I N T BO_ F I AE C EE__aO S E M E R , i l i l t l it t l l 1 I ' i' l i iil I HV_TG R HE TI NN P I PG D T EI U_DTiE F I LA I C __ I A C F O E N O SR E_EE I DA N X V D AE_RP A M R M PO R , i l 'l i ' ii l l i 'I l 3 i' l ii8 l L A RF - O E2 E_ F l B R O I I I E N T B A I HA HH-T YI E I NM AN PE CC H S EO R TR TR MU C L a DT TE CE RE C T NG EG O G NR SO AA JA P A OE I U T LN ON P N I EB TF PA RA U A N R I AD M PM S M I PH S A OD O C EA PE L T CE SEL P I V S ILE HEU R E TDF A T E O ., s N .L C U N T P N E R TR TR U R T DK TE CE RE E I C NG EG OG R G A SI AA JA PA A T ER LN ON PN N S PA RA UA A i RE M PM SM M PM 2 U I EL C @y E I T V I S N O , i ,i il iii'l l ,iI l ii8 l ,ii !l

A G t D Ai NR N S EE A TE S M NN N TO RGI I N NI ENE O A T PES A U N O I Y L Tl R I P R T L E S. A T A

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C OG l ECl R EP T RE U i O i N L S l I PA I C l T N E F l O I i S PN l S V R O RCR u E EES ER N UA D D li l l T T SM A A . TP T E F i O lil l j S l Ri l U SC ES EOT l I E I T T @ E O A T N R g ~ E ~ 0 0 P O L S TO O R - R R R N N R O S T O L ' O N PR R T OR R T T O US T N O N A S RO T-T' l S F F. I C l l V TT T A T l l R NA .A L R N l P E I A U A .R il T i E Oi TR P T E l S P S P A S R SP U .P CE SE T E O S L g S O S U P SP S P A S O AO P O F T G N N O R E I I E DK .R R T I C TE SO E T N A SI NG I PP C OP G R ER AA U RE LN SU N E PM PA E D N M N I E E L. O C G C I V L Y A L - K A R RR R C E OE F l P I C C T N I E TE O R S C lN N AN I Ul LI i l T iG UG C N E PR E N GN E O M UO 1 E EE T I P R g RP I I L AU T .TS A S. T Z P 2 P UU I 0 R S C R N E .B E V 1 A R G T C E R C 1 A A N Ea S G T ' ST S I P I I N I R S A c AP G U U N S O M a 2 P S E i U U S T /. P P T 1 j RO U N A. S R I T l A .E V SP I T' T' N T T E R L I N U N N E I 2S SP P I I I U SU A AG U A M ASI MN S L E ~ G S T ER .N E T iS R Rl T E SE C S I O OT C TI l P I i I L AN P N I j V M S A S R N NAI WI UI U E S R E El EE DG Y C I l AN T S Si St i RE P

l ADMINISTRATIVECONTROLS l 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG) FUNCTION 6.2.3.1 The ISEG shall function to examine unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of unit design and operating experience information, including units of similar design, which may indicate areas for improving unit safety. The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities, or other means of improving unit safety. Such recommendations shall be submitted through the General Manager-Nuclear Quality Assurance to the Senior Vice President-Nuclear. COMPOSITION 6.2.3.2 The Limerick ISEG shall be composed of at least three, dedicated, full-time engineers, including the ISEG Supervisor, located onsite. E6ch shall have a bachelor's j degree in engineering or related science and at least two years professional level experience in his or her field. The Limerick ISEG Supervisor shall have at least six years of exoerience in the nuclear field. The corporate ISEG shall be composed of two dcdicated full time engineers each with a Bachelors degree in engineering or related science and at least 2 years professional level experience in his or her field, at least 1 year of.which experience shall be in the nuclear field. The LGS ISEG reports to the Independent Safety Engineering Manager. 1 RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of unit activities to provide independent verification

  • that these activities are performed correctly and that human errors are reduced as much as practical.

RECORDS 6.2.3.4 Records of activities performed by the ISEG shall be prepared, maintained, and forwarded each calendar month to the Independent Safety Engineering Manager. 6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to Shift Supervision in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to safe operation of the unit. The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline and shall have received specific training in the response and analysis of the unit for transients and accidents, and in unit design and layout, including the capabilities of instrumentation and controls in the control room. ] 6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of unit staff shall meet or exceed the minimum qualifications of ANSI /ANS 3.1-1978 for comparable positions, except for the Senior Health Physicist who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. The licensed Operators and Senior Operators shall also meet or exceed the minimum qualifications of the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees.

  • Not responsible for sign-off function.

LIMERICK - UNIT 1 6-6 u.

g..- ADMINISTRATIVE' CONTROLS 6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be j maintained under the direction of the site Training organization and shall meet or I j exceed the. requirements of ANSI /ANS 3.1.-1978 and Appendix A of 10 CFR Part 55 and the 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. 6.5 ' REVIEW AND AUDIT I ~ 6.5.1 ' PLANT OPERATIONS REVIEW COMMITTEE (PORC) FUNCTIONf 6.5.1.1 The PORC shall function to ad' vise 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 Member: . Superintendent-Plant Services Member: Assistant Superintendent-0perations Member: Regulatory Engineer . Member: Technical Engineer Member: Shift Superintendent Member: Maintenance Engineer ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as' voting members in PORC activities at any one time. 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 6.5.1.5 The quorum of the PORC necessary for the performance of the PORC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and four members including alternates. LIMERICK - UNIT 1 6-7 b _________-__a

i

  • ADMINISTRATIVE CONTROLS RESPONSIBILITIES 6.5.1.6 The PORC shall be responsible for:-

a. Review of (1) all procedures required by Specification 6.8 and changes thereto, (2) all programs required by Specification 6.8 and changes thereto, and (3) any other procedures or changes thereto as determined by the Plant Manager to affect nuclear safety; b. Review of all proposed tests and experiments that affect nuclear safety; c. Review of all proposed changes to. Appendix A Technical Specifications; d. Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety; e. Review of the safety evaluations for procedures and changes thereto completed under the provisions of 10 CFR 50.59. f. Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evaluation and recommendations 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 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 Board. 1. Review of.every unplanned onsite release of radioactive material to the { i 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 Manager, and to the Nuclear Review Board. m. Review of changes to the PROCESS CONTROL PROGRAM, 0FFSITE DOSE CALCULATION MANUAL, and radwaste treatment systems. ] 6.5.1.7 The PORC shall: Recommend in writing to the Plant Manager approval or disapproval of a. items 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 6.5.1.6a through f. constitutes an unreviewed safety question. LIMERICK - UNIT 1 6-8

n. ci ADMINISTRATIVE CONTROLS RESPONSIBILITIES'(Continued) c. ' Provide written notification within 24 hours to the Vice President Limerick Generating Station and the Nuclear-Review Board of disagreement between the PORC and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1. RECORDS 6.5.1.8 The PORC shall maintain written minutes'of each PORC meeting that, at a minimum,- document the results of all PORC activities performed under the responsibility provisions of L these Technical Specifications. Copies shall be provided to the Vice President. Limerick Generating Station, Plant Manager, and the Nuclear Review Board. 6.5.2 NUCLEAR REVIEW BOARD (NRB) FUNCTION '6.5.2.1 The NRB shall function to provide independent review and audit of designated activities in the areas of: a. Nuclear power plant operations, b. Nuclear engineering.- c. Chemistry and. radiochemistry, d. Metallurgy, e. Instrumentation and control, f. Radiological safety, .g. Mechanical and electrical engineering, and h. Quality assurance practices. The NRB shall report to and advise the Senior Vice President-Nuclear and the Of fice of the Chief Executive on those areas of responsibility in Specifications:6.5.2.7 and 6.5.2.8. .l.i 1 COMPOSITION 6.5.2.2 The Chairman, members, and alternates of the HRB shall be appointed in. writing by the Senior Vice President-Nuclear, and shall have an academic degree in an engineering or I physical science field; and in addition, shall have a minimum of 5 years technical -. experience, of which a minimum of 3 years shall be in one or more areas given in Specification 6.5.2.1. The NRB shall be composed of no less than eight and no more than 12 j members. The members and alternates of the NRB will be competent in the area of Quality Assurance practice and cognizant of the Quality Assurance requirements of 10 CFR Part 50, Appendix B. -Additionally, they will be cognizant of the corporate Quality Assurance Program and will have the corporate Quality Assurance organization available to them. LIMERICK - UNIT 1 6-9 1 k

3,,l e ADMINISTRATIVE CONTROLS REVIEW (Continued) h. All. recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect' nuclear safety; and 1. Reports and meeting minutes of the PORC. AUDITS 6.6.2.8 Audits of unit a'ctivities shall be performed under the cognizance of the NRB. These audits shall. encompass: .. a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months; b. The performance, training and qualifications of the entire unit staff at least once per 12 months; c. The results of actions taken to correct. deficiencies occurring in unit equipment, structures, systems, or method of operation that affect nuclear safety, at least once-per 6 months; d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix B, 10 CFR Par 50, at least once per 24 months; e. The Emergency Plan and implementing procedures at least once per 12 j

months, f.

The Se.curity Plan and implementing procedures at least once per 12 months. g. Any other area of unit operation considered appropriate by the NRB or the Senior Vice President-Nuclear h. The fire Protection Program and implementing procedures at least once per 24 months. i. An independent fire protection and loss prevention inspection and audit shall be performed at least once p3r 12 months utilizing either 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 q. intervals no greater than 36 months. LIMERICK - UNIT 1 6-11 t

a s y.. - f> a,',. a ,, 5 '. Q. ' O

-.d 4 -

' M ~ ADMINISTRATIVE CONTR0'LS T T ' AUDITS (Continued) 'k. The radiological environmental'moriitoring program and the results thereof -at least once per'12 months. 1.y 'The 0FFSITE DOSE CALCULATION MANUAL.and implementing procedures at least' s .once'per,24 months. n i K m. sThe PROCESS CONTROL PROGRAM and implementing procedures.atcleast.once per '24, months. 'n.. The performance'of activities required by'the Quality Assurance Program to meet the criteria of Regulatory Guide.4.15, December, 1977,'at least conce per 12 months. RECORDS. t 6.5.2.9 Records of NR8' activities shall be:. prepared, approved, and distributed as

indicated below:

a. Minutes of each NRB meeting shall.be prepared, approved, and forwarded to ';,y the Senior Vice Preside-aclear within 14 days 'following each meeting. ~b'.

Reports'of. reviews encompassed-by Specification 6.5.2.7 shall be

~ ' prepared, approved, and. forwarded to the Senior Vice President-Nuclear within 14' days following completion of the. review. c. Audit reports encompassed by Specification 6.5.2.8 shall,be forwarded to the ' Senior Vice' President-Nuclear and to the management positions . responsible for-the areas audited within 30 days after completion of the. audit by the~ auditing organization. .6.6, REPORTABLE EVENT ACTION L 6.6.1 The following actions shall be taken for REPORTABLE EVENTS: a.; The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10'CFR'Part 50, and b'. 1:.Each REPORTABLE EVENT shall be reviewed by the PORC and submitted to the NRB,' Plant Manager, and the Vice President, Limerick Generating Station. l. I 6.7 'SAFEiYLIMITVIOLATION I ?6.7.1 The.following actions shall be taken in the event a Safety Limit is l

" violated

i f4 .a. Th'e NRC Operations Center shall be notified by telephone as soon as -possible and in all. cases within 1 hour. The Vice President, Limerick w t . Generating Station, Plant Manager, and the NRB shall be notified within 24 hours. } a

l

= LIMERICK ~- UNIT 1 6-12 AA l_l.._-_-_.---___.._---. a

cA'JhlTilSTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued) 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. c. The Safety Limit Violation Report shall be submitted to the Commission, the NRB, Plant Manager, and the Vice President Limerick Generating Station, within the 14 days of the violation. 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: a. The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2. February 1978. b. The applicable procedures required to implement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737. c. Refueling operations, d. Surveillance and test activities of safety-related equipment, e. Security Plan implementation. f. Emergency Plan implementation. g. Fire Protection Program implementation. h. 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, shall be reviewed in accordance with Specification 6.5.1.6 and shall be approved by the Plant Manager or designee prior to implementation and reviewed periodically as set forth in administrative procedures. 6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made provided: a. he intent of the original procedure is not altered; 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 c. The change is documented, reviewed by the PORC, and approved by the Plant Manager or designee within 14 days of implementation. 'IMERICK - UNIT 1 6-13 im}}

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