ML20044B278

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Proposed Tech Spec Section 6.0 Re station-qualified Reviewer Program
ML20044B278
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 07/13/1990
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20044B275 List:
References
NUDOCS 9007180267
Download: ML20044B278 (13)
v • d • e


Text

.

y-. ATTACHMENT 2 PEACH BOTTOM ATOMIC. POWER STATION-UNITS 2 and 3 f

Docket Nos. 50-277-50-278 License Nos. DPR-44 DPR-56 REVISED TECHNICAL SPECIFICATION PAGES List of Attached Pages

, 247 248 252a 253

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254 260 9007180267 900713 e i

-p PDR ADOCK 05000277 P- PDC 1

y, UNIT 2 1

l Meeting Frequency .

J6.5.1.4- The PORC shall meet at least once per calendar month and as convened by the PORC Chairman or his designated alternate (s).

Quorum

6.5.1.5 A quorum of the PORC necessary for the performance of the PORC  !

responsibilities and authority provisions of these. Technical Specifications shall consist of the Chairman or his designated alternate (s) and four members or their alternates. '

Responsibilities 76.5.1.6 The Plant Operations Review Committee shall.be responsible for:

a. .Reviewof1)Administrativeproceduresandchangesthereto,2) new procedures requiring a 10 CFR 50.59 safety evaluation, and
3) proposed changes to procedures requiring a 10 CFR 50.59 safety evaluation.
b. Review of all proposed tests and experiments that~ affect

- nuclear safety.' a

c. Review of.all proposed changes to the Techn'ical Specifications. y
d. . Review of all proposed changes or nodifications to plant systems c/ equipment that affect nuclear safety..
e. Investigation of all violations of the Technical' Specifications and shall prepare and forward a report covering evaluation and ,

recommendations to' prevent recurrence to the Plant Manager, the_

Vice President, Peach Bottom-Atomic Powen Station, and Lthe Nuclear Review Board.

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

+

g. Performance of special reviews and investigations and reports i thereon as requested by the Chairman of the Nuclear Review Board. ,
h. Review of all reportable events required by 10 CFR 50.73.

[:

-247-i L

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UNIT 2- [

, PBAPS

'6... 5 1 6 Continued- t

1. Review of'the Plant Security Plan and implementing procedures, and shall submit recomended-changes to the Plan to the Plant Manager and the Nuclear Review Board.

-j . Review of the Emergency Plan and implementing procedures, and ,

shall' submit recomended changes to the Plan to the Plant Manager and the Nuclear Review Board. .>

I

k. Review of every unplanned release reportable under 10CFR 50.72 and 50.73, of radioactive material to the environs; evaluate the event;'specify remedial action to prevent recurrence; and document the event description, evaluation, and corrective action and the' disposition of the corrective action in the 4

_ plant records.

Authority 6.5.1.7 - The Plant _.0perations' Review Comittee shall: ,

. . -i

a. Recomend in writing, to the Plant Manager, for his approval or  ;

disapproval'ofitemsconsideredunder6.5.1.6(a)through(d) ,

above.

b. -Render determinations in writing with regard to whether or not'

, each item considered under 6.5.1.6(b) through (e) above l constitutes an unreviewed safety questioti, as defined in 10~ CFR '

50.59.-

'2

- c. Provide imediate writt'en notification to the Vice President, Peach Bottom Atomic Power Station, or in his absence, the

Executive'Vice President - Nuclear 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 6.1.1 above.- ,

e s

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q UNIT 2'

., PBAPS '

j c.O Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Executive Vice President-Nuclear, and to the management positions responsible for 1

'the areas audited within 30 days after completion of the audit .

i b

6.5.3 Procedure Review and Approval 6.5.3.1 Each new procedure and procedure change shall be reviewed by a Station 4

Qualified lleviewer (SQR) who is knowledgeable in the functional area j affected but is not the individual who prepared the new procedure or procedure change. The SQR may be from the same organization as the preparer. The SQR shall render a detemination in writing of whether or not i cross-disciplinary review of the new procedure or procedure change is necessary. If necessary, such review shall be performed by appropriate personnel.

6.5.3.2 Each new procedure or procedure change shall be reviewed by the

Superintendent designated by Administrative procedures as the responsible p Superintendent for that procedure, and:the review shall include a determination of whether or not a 10 CFR 50.59 Safety Evaluation is required. If a Safety Evaluation is not required, the new procedure or procedure change shall be approved by the responsible Superintendent.or the  !

Plant Manager prior to implementation. Administrative procedures (and ' '

l changes thereto) shall be reviewed by'PORC prior to approval.

Administrative procedures, Security Plan implementing procedures, Emergency  !

Plan' implementing procedures and changes thereto shall be approved by the l Plant Manager or his designated alternate in accordance with Specification j

.6.1.1.

6.5.3.3 If the responsible Superintendent determines that a new procedure or 1

procedure change-requires a 10 CFR 50.59 safety evaluation, the responsible

-Superintendent shall render a determination.in writing of whether or not the ,

new procedure or procedure change involves an Unreviewed Safety Question

(USQ), and shall forward the new procedure or. procedure change with the associated safety evaluation to PORC for review.- If an USQ is involved, NRC v approval is required by 10 CFR 50.59 prior to implementation of the new <

procedure or procedure change.

6.5.3.4 Personnel recoisnended 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.  !

6.5.3.6 Records documenting the activities perfonned under Specifications 6.5.3.1 s tnrough 6.5.3.5 shall be maintained in accordance with Specification 6.10.

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UNIT 2--

PBAPS 6.6 R_eportable Event Action 6.6.1 The following actions-shall be taken for Reportable Events:

a.- The Commission shall be notified pursuant to the requirements of

-Section 50.73 to 10 CFR 50.

b. - Each Reportable Event Report submitted to the Comission shall be reviewed by the PORC and submitted to the NRB and the Vice President.

Peach Bottom Atomic Power 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 provisions of 10 CFR 50.36(c)(1)(i) shall be complied with immediately,
b. The NRC 0perations Center shall be notified by telephone as soon as possible and-in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The Vice President Peach-

. Bottom Atomic Power Station, Plant Manager, and the NR8 shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PORC. Thisreportshalldescribe(1) applicable circumstancesprecedingtheviolation,(2)effectsoftheviolation

-upon facility components, systems or structures,-and (3) corrective action;taken to prevent recurrence.

d. The Safety Limit Violation Report shall be submitted to the Comission, the NRB and the-Vice President, Peach Bottom Atomic Power Station within 10 working days of the violation.

6.8 Procedures 6.8.1 Written procedures and administrative policies,shall be established.

. implemented and maintained as follows, ext.ept as provided in Technical

- Specifications 6.8.2 and 6.8.3:

a. Frucedures that meet the requirements of Sections 5.1 and 5.3 of ANSI N18.7-1972
b. Procedures that meet the requirements of Appendix "A" of USAEC Regulatory Guide 1.33 (November 1972)
c. Procedures' covering radiological effluent technical specification activities, including the Offsite Dose Calculation Manual and Quality Assurance Program for environmental monitoring using the. guidance in Regulatory Guide 4.1, Revision 1. April 1975.

, -253-

1 UNIT 2 PBAPS e

6,8.2 Each procedure and administrative polic) of Technical 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 Technical Specification 6.5.3 (and 6.5.1.6.a and 6.5.1.7.a. if required) prior to implementation.

Each procedure of Technical Specification 6.8.1 shall also be reviewed periodically as set forth in Administrative procedures.

6.8.3 Temporary changes to procedures of' Technical Specification 6.8.1 above l may be made, provided:

a. The intent of the original procedure is not altered.
b. The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.

c.

i Within 14 days of implementation, the change is documented, reviewed by an SQR in accordance with Technical Specification 6.5.3.1, and approved by.either the Plant Manager (or his designated alternate in accordance with Technical Specification 6.1.1) or the Superintendent cesignated by Administrative procedures as the responsible Superintendent for that procedure, ti.8. 4 (Relocated into 6.8.1.c) 6.9 Reporting Requirements In addition to the applicable reporting requirements of Title 10, Code of federal Regulations, the following identified reports shall be submitted to the administrator of the appropriate Regional Office unless otherwise noted. I

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l l ~254-

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UNIT 2' PBAPS 3

6.10 Record Retention 6.10.1 The following records shall be retained for at least five years:

a. Records and logs of facility operation covering' time interval at each power level.
b. Records and logs of principle maintenance activities, inspections, repair and replacement of principle items of equipment related te nuclear safety,
c. Reportable Event Reports required by 10 CFR 50.73.
d. Records of surveillance activities, inspections and calibrations required by these Terhnical Specifications.
e. Records of reactor tests and experiments.
f. - Records of changes made to procedures required by Specification 6.8.
g. Records of radioactive shipments.

.. h. Recort.s if sealed source leak tests and rebults.

, 1. Records of annual physical inventory of all source material of record.

U 6.10.2 The following records shall be retained for the duration of the Facility Operating License

a. Record and drawing changes reflecting facility a design modifications made to systemr. and equipment '

described in the Final Safety Analysis Report.

b. Records of new and irradiated fuel inventory, fugl transfers and assembly burnup histccles.
c. Records of facility radiation and contaminatlon surveys.

1 4

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i UNIT 3 l

PBAPS i

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 (s).  ;

l Quorum i t

6.5.1.5 A quorum of the PORC necessary for the performance of the PORC l responsibilities and authority provisions of these Technical i Specifications shall consist of the Chairman or his designated  ;

alternate (s)andfourmembersortheiralternates.

i Responsibilities 6.5.1.6 The Plant Operations Review Committee shall be responsible for:

a. Reviewof1) Administrative'proceduresandchangesthereto,2) new procedures requiring a 10 CFR 50.59 safety evaluation, and
3) proposed changes to procedures requiring a 10 CFR 50.59 .

safety evaluat. ion,

b. Review of all proposed tests and experiments that affect nucicar safety.
c. Review of all proposed changes to the Technical Specifications. ,
d. Review of all proposed changes or modifications to plant >

systems or equipment that affect nuclear safety.

e. Investigation of all violations of the Technical Specifications i and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence to the Plant Manager, the Vice President. Peach Bottom Atomic Power Station, and the Nuclear Review Board. '
f. Review of facility operatio'ns to detect potential safety hazards.

-g. Performance of special reviews and investigations and reports thereon as requested by the Chairman of the Nuclear Review Board.

h. Review of all reportable events required by 10 CFR 50.73.

l L -247-L u-l

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PBAPS Unit 3 6.5.1.6 Continued l

i. Review of the Plant Security Plan and implementing procedures, j and shall submit recomended changes to the Plan to the Plant 1 Manager and the Nuclear Review Board,
j. Review of the Emergency Plan and implementing procedures, and shall submit recomended changes to the Plan to the Plant Manager and the Nuclear Review Board.

L

k. Review of every unplanned release reportab'9 under 10CfR 50.72 and 50.73, of radioactive material to the invirons; evaluate j the event; specify remedial action to prevert recurrence; and e

document the event description, evaluation, and corrective .

action and the disposition of the corrective action in the  !

plant records, s

Authority 6.5.1.7 The Plant Operations Review Comittee shall:

i

a. Recomend in writing, to the Plant Manager, for his approval or disapprovalofitemsconsideredunder6.5.1.6(a)through(d) ,

above. l

b. Render determinations in writing with regard to whether or not ,

each item considered under 6.5.1.6(b) through (c) above l l constitutes an unreviewed safety question, as defined in 10 CFR '

'50.59. -

c. Provide imediate written notification to the Vice President.

Peach Bottom Atomic Power Station, or in his absence, the Executive Vice President - Nuclear and the Nuclear Review Board of disagreement between the and the Plant Manager ,

however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above. i t

-248-t L

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l UNIT 3 PBAP!

c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Executive Vice President-Nuclear, and to the management positions responsible for '

the areas audited within 30 days after completion of the audit.

6.5.3 Procedure Review and Approval 6.5.3.1 Each new procedure and procedure change shall be reviewed by a Station Qualified Reviewer (SQR) who is knowledgeable in the functional area affected but is not the individual who prepared the new procedure or  ;

procedure change. The SQR may be from the same organization as the preparer. The SQR shall rendee a determination in writing of whether or not ,

cross-disciplinary review of the new procedure or procedure change is '

i necessary. If necessary, such review shall be performed by appropriate i personnel.

i 6.5.3.2 Each new procedure or procedure change shall be reviewed by the Superintendent des!gnated by Administrative procedures as the responsible e Superintendent for that procedure, and the review shall include a  !

determination of whether or not a 10 CFR 50.59 Safety Evaluation is required. If a Safety Evaluation is not required, the new procedure or procedure change shall be approved by the responsible Superintendent or the '_

Plant Manager prior to implementation. Administrative procedures (and changes thereto) shall be reviewed by'PORC prior to approval.

Administrative procedures, Security Plan implementing procedures Emergency Plan implementing procedures and changes thereto shall be approved by the Plant Manager or his des,ignated alternate in accordance with Specification 6.1.1.

-6.5.3.3 If the responsible Superintendent detennines that a new procedure or procedure change requires a 10 CFR 50.t4 safety evaluation, the responsible Superintendent shall render a determination in writing of whether or not the new procedure or procedure change involves an Unreviewed Safety Question (USQ), and shall forward the new procedure or procedure change with the i 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 procedure or procedure change.

6.5.3.4- Personnel reconnended to be SQRs shall be approved and designated as such by  :

I the PORC Chairman. The responsible Superintendents shall ensure that a L

i sufficient complement of SQRs for their functional area is maintained in accordance with Administrative procedures, ,

t >

h 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 through 6.5.3.5 shall be maintained in accordance with Specification 6.10.

-252a-

  • , UNV,T 3 1

PBAPS  !

6.6 Reportable Event Action o 6.6.1 The following actions shall be taken for Reportable Events: 1 1

a. The Comission shall be notified pursuant to the requirements of Section 50.73 to 10 CFR 50.
b. Each Reportable Event Report submitted to the Comission shall be reviewed by the PORC and submitted to the NRB and the Vice President, Peach Bottom Atomic Power Station. ,

6.7 Safety Limit Violation 6.7.1 The following actions shall be taken in the event a Safety Limit is  ;

violated:

a. Theprovisionsof10CFR50.36(c)(1)(1)shallbecompliedwith imediately.
b. The NRC Operations Center shall be nitified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The Vice President, Peach Bottom Atomic Power Station, Plant Manager, and the NRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. .
c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PORC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence. '
d. The Safety Limit Violation Report shall be submitted to the Comission, -

the NRB and the Vice President Peach Bottom Atomic Power Station within 10 working days of the violation.

i 6.8 Procedures  !

6.8.1 Written procedures and administrative policies shall be established, implemented and maintained as follows, except as provided in Technical Specifications 6.8.2 and 6.8.3:

a. Procedures that meet the requirements of Sections 5.1 and 5.3 of ANSI N18.7-1972 1
b. Procedures that meet the requirements of Appendix "A" of USAEC t RegulatoryGuide1.33(November 1972) '
c. Procedures covering radiological effluent technical specification

' activities, including the Offsite Dose Calculation Manual and Quality Assurance Program for environmental monitoring using the guidance in Regulatory Guide 4.1, Revision 1. April 1975.

t -

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UNIT 3 [

P8APS 6.8.2 Each procedure and administrative policy of Technical Specification .

6.8.1 and changes thereto, and any other procedure or procedure change i that the Plant Manager determines to affect nuclear safety shall be reviewed and approved in accordance with Technical Specification 6.5.3 (and 6.5.1.6.a and 6.5.1.7.a. If required) prior to implementation.

Each procedure of Technical Specification 6.8.1 shall also be reviewed '

periodically as set forth in Administrative procedures.

6.8.3 Temporary changes to procedures of Technical Specification 6.8.1 above I may be made, provided:

a. The intent of the original procedure is not altered,
b. The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's ,

License on the unit affected.

c. Within 14 days of implementation, the change is documanted, reviewed by an SQR in accordance with Technical Specification - 6.5.3.1, and approved by either the Plant Manager (or his  ;

designated alternate in accordance with Technical Specification '

6.1.1) or the Superintendent designated by Administrative procedures as the responsible Superintendent for that procedure. -

6.8.4 (Relocatedinto6.8.1.c) 6.9 Reporting Requirements In addition to the applicable reporting requirements of Title 10. Code of federal Regulations, the following identified reports shall be submitted to the administratcr of the appropriate Regional Office '

unless otherwise noted.

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.. *c- UNIT 3 I PBAPS f . -

6.10 Record Retention '

'6.10.1 The following records shall be retained for at least five-years: l l

a. Records and logs of facility operation covering >

time interval at each power level. '

b. Records and logs of principle maintenance activities, inspections, repair-and replacement of principle items of equipment.related to nuclear j safety.
c. Reportable Event Reports required by 10 CFR 50.73..

I

d. Records of surveillance activities, inspections and calibrations required by these Technical l Specifications.  ;
e. Records of reactor tests and experiments.

i

f._
Records of changes made to procedures required by  ;

g Specification 6.8.

L g.

Records of radioactive shipments.

J h.- -Records of sealed source leak tests and results. i i

1. Records of annual physical inventory of'all source ,

material of record. .

e s .-

6.10.2- The following records shall be ratained for the duration of the Facility Operating Licenses i e

a.

L Record and drawing changes reflecting facility .{

design modifications made to systems and equipment '

described in the. Final Safety Analysis Report.

b.. Records'of'new and irradiated fuel inventory, fuel >

, transfers and assembly burnup histories. ,

c. . Records of facility radiation and contamination  :

surveys.  !

,c T i

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