Text

Proposed Tech Spec Section 6.0 Re station-qualified Reviewer Program
	ML20044B269
Person / Time
Site:	Limerick
Issue date:	07/13/1990
From:	; PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	;
Shared Package
ML20044B268	List: ML20044B267; ML20044B269;
References
	NUDOCS 9007180250
	Download: ML20044B269 (13)
	v • d • e

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ATTACHMENT 2 I

LIMERICK GENERATING STATION 1

n Docket Nos. 50-352 50-353

.__ License Nos. NPf-39 NPF-85 PROPOSED TECHNICAL SPECIFICATIONS CHANGES List of Attached Change Pages Unit 1 xxvii

, 6-8 6-12 6-12a 6-13 6-19 Unit 2 xxvii 6-8 e 6-12

l. 6-12a l 6-13 6-19 l'

9007180250 900713 e PDR ADOCK 05000352

.p PDC

1. , -

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m INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.5.2 NUCLEARREVIEWBOARD(NRB)

Function..................................................... 6-9 Composition.................................................. 6-9 Alternates................................................... 6-10 Consultants.................................................. 6-10 Meeting frequency............................................ 6-10 Quorum....................................................... 6-10 Review....................................................... 6-10 Audits....................................................... 6-11 Records...................................................... 6-12

-6.5.3 PROGRAM / PROCEDURE REVIEW AND APPROVAL 6-12 6.6 REPORTABLE EVENT ACTI0N.......................................... 6-12a 6.7 SAFETY LIMIT V10LATION........................................... 6-12a 6.8 PROCEDURES AND PR0 GRAMS.......................................... 6-13 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE. REPORTS............................................. 6-15 Startup Report.............................................. 6-15 Annual Reports.............................................. 6-15

Monthly Operating Reports...... ............................ 6-16 Annual Radiological Environmental Operating Report.......... 6-16 Semiannual Radioactive Effluent Release Report.............. 6-17 6.9.2 SPECIAL REP 0RTS............................................. 6-18 6.9.3 CORE OPERATING LIMITS REP 0RT................................ 6-18a 6.10 RECORD RETENTION............................................... 6-19 l

6.11 RADIATION PROTECTION PR0 GRAM................................... 6-20 6.12 HIGH RADIATION AREA............................................ 6-20 LIMERICK - UNIT 1 xxvii

ADMINISTRATIVE CONTROLS

. *RES'POWSIBILITIES 6.5.1.6 The PORC shall be responsible for: '

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 50.59 safety evaluation;

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; l

e. DELETED.

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. Perfonnance of special reviews, investigations, or analyses and reports l thereon as requested by the Vice President, Limerick Generating Station, Plant Manager or tne Chairman of the Nuclear Review Board;

l j. Review of the Security Plan and implementing procedures and submittal of i recommended changes to the Nuclear Review Board; and ;

l'

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 Manager -and to the Nuclear Review Boara,

m. Review of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and radwaste treatment systems.

6.5.1.7 The PORC shall:

a. Recommend in writing to the Plant Manager approval or disapproval of 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 considered under Specification 6.5.1.6b. through f. constitutes an unreviewed safety question. l LIMERICK - UNIT 1 6-8 4 -

ADMINISTRATIVE CONTROLS I

AUDITS (Continued)

k. The radiological environmental monitoring program and the results thereof !

at least once per 12 months. ;

1. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least i once per 24 months, i

m. The PROCESS CONTROL PROGRAM and implementing procedures at least once per 24 months. ;

n. The performance of activities required by the Quality Assurance Program i to meet the criteria of Regulatory Guide 4.15, December, 1977, at least once per 12 months. ;

RECORDS -

6.5.2.9 Records of NRB activities shall be prepared, approved, and distributed as !

indicated below:

a. Minutes of each NRB meeting shall be prepared, approved, and forwarded to the Executive Vice President - Nuclear 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 Executive Vice President -

l l

Nuclear within 14 days following completion of the review. >

c. Audit reports encompassed by Specification 6.5.2.8 shall be forwarded to 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.

l 6.5.3 PROGRAM / PROCEDURE REVIEW AND APPROVAL

, All programs and procedures required by Specification 6.8 shall be reviewed and [

l approved as-described below. '

l-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 individual 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 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 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 1 6-12

f

)

ADM,1NISTRATIVE CONTROLS f

o' ,

l 6.5.3.3 If the responsible Superintendent determines that a new program, 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 pr i question (USQ)yram, procedure,orchangetheretoinvolvesanunreviewedsafety

, 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 approval is required by 10 CFR 50.59 prior to implementation of the new -

program, procedure, or change.

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.

6.5.3.5 Temporary procedure changes shall be reviewed and approved in accordance with Specification 6.8.3. r 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:

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. 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:

a. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The Vice President. Limerick '

Generating Station, Plant Manager, and the NRB shall be notified within

'24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . -

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 L to prevent recurrence.

l l 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.

LIMERICK - UNIT 1 6-12a l

l l

l

ADMINISTRATIVE CONTROLS CSAFITVLIMITVIOLATION(Continued) i

d. Critical operation of the unit shall not be resumed until authorized by l the Commission, j

6.8 PROCEDURES AND PROGRAMS 6.8.1 Writtan procedures shall be established, implemented, and maintained 1 covering the activities referenced below: !

1

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 i NUREG-0737 and Supplement 1 to NUREG-0737. I

c. Refueling operations. j d.. Surveillance and test activities of safety-related equipment. I

e. Security Plan implementation. >

f. Emergency Plan implementation.

g. . Fire Protection Program implementation. '

h. PROCESS CONTROL PROGRAM implementstion.

1. OFFSITE DOSE CALCULATION MANUAL inolementation.

j. Quality Assurance Program for effluent and environmental monitoring, I 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 Ifanager determines to affect nuclear safety, shall be reviewed and approved in acccrdance with Specifications 6.5.1.6, 6.5.1.7 and/or 6.5.3, as 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 -

provided:

1. The intent of the original procedure is not altered; t,'. The change is approved by two members of the unit managemeni staff, at least one of whom holds a Senior Operator license on the unit affected; and

c. The change is documented, reviewed by an 50R in accordance with 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 Superintendent designated by Administrative Procedures as the responsible Superintendent for that procedure within 14 days of implementation, t

1.1MERICK - UNIT 1 6-13

,. ADMINISTRATIVE CONTROLS !

l 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 l the minimum period indicated.

)

6.10.2 The following records shall be retained for at least 5 years:

a. Records and logs of unit operation covering time interval at each power l 1evel.

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. '

d. Records of' surveillance activities, inspections, and calibrations required by these Tt;hnical Specifications,

e. Records of changes made to the programs and procedures required by >

Specification 6.8. i

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 i Operating License:

,' a. Records and drawing changes reflecting unit design modifications made to L

systems and equipment described in the Final Safety Analysis Report.

b. Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories. 1

c. Records of radiation exposure for all individuals entering radiation control areas.

t LIMERICK - UNIT 1 6-19 -

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.5.2 NUCLEARREVIEWBOARD(NRB)

Function..................................................... 6-9 Composition.................................................. 6-9 Alternates................................................... 6-10 Consultants.................................................. 6-10 Meeting Frequency............................................ 6-10 Quorum....................................................... 6-10 Review....................................................... 6-10 Audits....................................................... 6-11 Records...................................................... 6-12 6.5.3 PROGRAM / PROCEDURE REVIEW AND APPROVAL 6-12 6.6 REPORTABLE EVENT ACT10N.......................................... 6-12a 6.7 SAFETY LIMIT V10LATION........................................... 6-12a 6.8 PROCEDURES AND PR0 GRAMS.......................................... 6-13

_ 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REP 0RTS............................................. 6-15 Startup Report.............................................. 6-15 Annual Reports.............................................. 6-15 -

Monthly Operating Reports...................... 4........... 6-16 Annual Radiological Environmental Operating Report.......... 6-16 Semiannual Radioactive Effluent Release Report.............. 6-17 6.9.2 .SPECIAL REP 0RTS............................................. 6-18 6.9.3 CORE OPERATING LIMITS REP 0RT................................ 6-18a m

6.10 RECORD RETENT10N............................................... 6-19 6.11 RADIATION PROTECTION PR0 GRAM................................... 6-20 6.12 HIGH RADIATION AREA............................................ 6-20 1

LIMERICK - UNIT 2 xxvii

.,. ,AD MINISTRATIVE CONTROLS l

. \

.. RESPONSIBILITIES l

6.5.1.6 The PORC shall be responsible for:

a. Reviewof(1)AdministrativeProceduresandchangesthereto,(2)new programs or procedures required by Specification 6.8 and requiring a 10 CFR 50,59 safety evaluation, and i required by Specification 6.8(and requiring a 10 CFR 50.59 safety 3)propos i evaluation; - i

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

c. Review of all proposed changes to Appendix A Technical Specifications; s

d. Review of all proposed changes or modifications to unit systems or equipment ;

that affect nuclear safety; I

e. DELETED.

1

f. Investigation of all violations of the Technical Specifications, including I the preparat' ion and forwarding of reports covering evaluation and recomendations to prevent recurrence, to the Vice President. Limerick Generating Station, Plant Manager, and to the Nuclear Review Board l

g. Review of all REPORTABLE EVENTS; J

h. Review of unit operations to detect potential hazards to nuclear safety;

i. Performance of special reviews, investigations, or analyses and reports I 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, OFFSITE DOSE CALCULATION MANUAL, and radwaste treatment systems. ,

6.5.1.7 The PORC shall:

a. Recorkmend in writing to the Plant Manager approval or disapproval of 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 considered under Specification 6.5.1.6b. through f. constitutes an l unreviewed safety question.

LIMERICK - UNIT 2 6-8 L

. - , ADMINISTRATIVE. CONTROLS a

l AUDITS (Continued) l

k. The radiological environmental monitoring program and the results thereof at least once per 12 months. !

1. The OFFSITE DOSE CALCULATION MANUAL and implementing procedtres at least !

once per 24 months.

I

+ m. The PROCESS CONTROL PROGRAM and implementing procedures at least once per I 24 months. I

n. The performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 4.15 December, 1977, at least once per 12 months.

l k

RECORDS

(

6.5.2.9 Records of HRB activities shall be prepared, approved, and distributed as l indicated below: l

- a. Minutes of each NRB meeting shall be prepared, approved, and forwarded to ;

the Executive Vice President - Nuclear 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 Executive 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 Corporate Officer (s) and management positions responsible for the areas auditad within 30 days after completion of the audit by the auditing organization.

6.5.3 PROGRAM / PROCEDURE REVIEW AND APPROVAL 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 ange thereto shall be independently -

reviewed by a Station Qualified Reviewer (SQR) who is knowledgeable in the functional area affected but is not the individual 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 shall be performed by

l appropriate personnel.

l' 6.5.3.2 Each new program, procedure, nr change-thereto shall be reviewed by the i 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 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 besignated alternate in accordance with Specification 6.1.1. !

, LIMERICK - UNIT 2 6-12

I g ' ADMINISTRATIVE CONTROLS ,

~ .

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 Superintendent shall render a determination in writing of whether or not the new program, procedure,orchangetheretoinvolvesanunreviewedsafetyquestion(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 approval is !

required by 10 CFR 50.59 prior to implementation of the new program, procedure, or change.

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' i complement of SQRs for their functional area is maintained in accordance with !

Administrative Procedures.

6.5.3.5 Temporary procedure changes shall be reviewed and approved in accordance with Specification 6.8.3.

6.5.3.6 Records documenting the activities performed under Specifications 6.5.3.1 l through 6.5.3.5 shall be maintained in accordance with Specification 6.10.

6. _6 REPORTABLE EVENT ACTION l

l-6.6.1 The following actions shall be taken for REPORTABLE EVENTS: .

a. The Commission shall be not'fied and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and i

b. Each REPORTABLE EVENT shall be reviewed by the PORC and submitted to the

) NRB, Plant Manager and the Vice President, Limerick Generating Station.

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

, a. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The Vice President, Limerick Generating Station, Plant Manager, and the NRB shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . '

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, Plcnt Manager, and the Vice President, Limerick Generating Station, within the 14 days of the violation.

LIMERICK - UNIT 2 6-12a l

:.. O DNINIST.RATIVE! CONTROLS K SAFETY LIM!T VIOLATION (Continued) l E d. Critical operation of the unit shall not be resumed until authorized by I the Commission.

1

.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 I to NUREG-0737, c.- Refueling operations,

d. Surveillance and test activities of safety-related equipment,

e. Secur'iy Plan implementation.

f.- Emergency Plan-implementation.

g .' Fire Protection Program implementation,

b. PROCESS CONTROL PROGRAM implementation.

, .1.- 0FFSITE DOSE CALCULATION MANUAL' implementation.

J. Quality Assurance Program for effluent and environmental monitoring, o using the guidance of Regulatory Guide 4.15, February 1979.

t 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- ,

4 safety, shall.be reviewed and; approved in-accordance with Specifications 6.5.1.6,-

6.5.1.7 and/or 6.5.3,.as appropriate, prior to' implementation. Each procedure of

~ Specification 6'8.1:shall also be reviewed periodically _as set forth in Administrative Procedures. ,

L6.8.3- Temporary changes to procedures of Specification 6.8.1 may be made' -

provided:

e a. -The 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; e and-

c. The change is documented, reviewed by an SQR in accordance with

! Specification 6.5.3.1, and approved by either the Plant Manager or his h designated alternate in accordance with *pecification 6.1.1, or the L

Superintendent designated by Administrative Procedures as the responsible Superintendent for that procedure within 14 days of implementation.

LIMERICK - UNIT 2 6-13

= _ _-_______ _ _ - __.

y .

p 2).?,.4 k.ADMINISTRATIVECONTROLS ,

6.10 RECORD RETENTION 6.10.1 In addition to the applicable record reteation requirements of Title 10, Code of Federal Regulations,-the following records shall be retained for at least the minimum-period indicated.

6.10.2 The following records shall be retained for at least 5 years:

, a. Records and logs of unit operation covering time interval at each power level,

b. Records and logs of principal maintenance activities, inspections, repair, and repiscement of principal items of equipment related to nucler.r safety,

c. All REPORTABLE EVENTS.

d. Records of surveillance activities, inspections, and calibrations:

reqeired by these Technical Specifications.

e. Recoru i changes made to the programs and procedures required by Specification 6.8.

d

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 auration of the unit:

Operating License:

a. Records and drawing changes reflecting unit design modifications made to systems and equipment describad in the Final Safety Analysis Report.

b. Records of new and irradiated fuel inventory, fuel transfers, and

. assembly burnup histories,

c. Records of radiation exposure for all individuals entering radiation 7 , control areas.

.i N-LIMERICK - UNIT 2 6-19

_.

ML20044B269

Text

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