ML20065B947

Proposed Tech Specs,Reflecting Relocation of TS Fire Protection Requirements to UFSAR

ML20065B947
Person / Time
Site:	Peach Bottom
Issue date:	03/28/1994
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20065B946	List: ML20065B944 ML20065B947
References
NUDOCS 9404040219
Download: ML20065B947 (17)

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ATTACHMENT 2 l

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PEACH BOTTOM ATOMIC POWER STATION i UNITS 2 AND 3 Docket Nos. 50-277 50-278 Ucense Nos. DPR-44 DPR-56 TECHNICAL SPECIFICATION CHANGE REQUEST 90-05

" Relocation of Technical Specifications Fire Protection Requirements to the Updated Final Safety Analysis Report" i

Ust of Revised Pages  ;

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. Unit.2 Unit 3 FOL6 FOL6 l 240c thru 240s 240c thru 240s 244 244 246 246 248 248 1 252 252  !

253 253 l I

1 940404o219 94o328 PDR ADOCK 05o00277

. through July 9, 1986; and " Peach Bottom Atomic Power Station, Units 2 and 3 Safeguards Contingency Plan," with revisions submitted through March 10, 1981. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

(5) PECO Energy Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility, and as approved in the NRC Safety Evaluation Report dated September 16, 1993, subject to the following provision:

PECO Energy Company may make changes to the approved fire ,

protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire. .

3. This amended license is subject to the following conditions for the protection of the environment:

(a) Upon completion of the licensees' " smoke tests," the licensees shall release all procedures, data, and analysis bearing on the calculation of X/Q to the Regulatory Staff as soon as possible but no later than initial fuel loading for Peach Bottom Unit 3. Using the " smoke test" results to re-calculate X/Q' >

and using the other assumptions previously used by the Regulatory Staff (or.

realistic refinements thereof), the Regulatory Staff shall re-calculate the potential radiciodine thyroid dose to a child via the milk pathway at the points of maximum concentration at or beyond the site boundary where dairy cows are present or could be pastured. If this calculated dose based on the combined operation of Peach Bottom Units 2 and 3 exceeds 15 mrem / year, then the licensees shall install for operation no later than the next refueling Page 6 l

d

. March 10, 1981. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

(4) PECO Energy Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility, and as approved in the NRC Safety Evaluation Report dated September 16, 1993, subject to the following provision:

PECO Energy Company may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

(5) Operation beyond the end-of-cycle (all rods out condition) thermal power is limited to seventy (70) percent minimum. Increasing core power level via reduced feedwater heating, once operation in the coastdown mode has begun, is not permitted unless the licensee has performed an analysis of this operating condition that confirms that this condition is bounded by the analysis for the particular cycle of operation.

3. This license is subject to the following conditions for the protection of the environment:

A. If the actual milk sample measurements taken at the nearby farms in accordance with the Technical Specifications, predict a dose to a child's thyroid, based on actual combined operation of Unit 2 and Unit.3, that exceeds 15 mrem / year, licensees shall install for operation no later than Page 6

, Unit 2 PBAPS The Fire Protection Limiting Conditions for Operation and Surveillance Requirements have been relocated to the Fire Protection Program, which is part of the UFSAR. These requirements are still mandated by the Facility Operating License.

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Unit 3 ,

PBAPS The Fire Protection Limiting Conditions for Operation and Surveillance Requirements have been relocated to the Fire Protection Program, which is part of the UFSAR. These requirements are still mandated by the Facility Operating License.

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t Unit 2 PBAPS

- Continued 6.2.2 Facility Staff The facility organization shall be subject to the following:

a. Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2.1, except that the shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

b. At least one licensed operator shall be in the control room and assigned to each reactor that contains fuel.

c. At least two licensed operator; excluding the operator on the second unit, shall be present in the control room during reactor startup, scheduled reactor shutdown and during recovery from reactor trips,

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

e. All CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator -

Limited to Fuel Handling who has no other concurrent respon-sibility during this operation.

f. Deleted.

g. In addition to the requirements of 6.2.2.a. the following shall hold a senior reactor operator license: 1) Plant Manager or Superintendent-0perations, 2) Assistant Superintendent-0perations and 3) Superintendent-Technical or Engineer-Systems.

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1 Unit 3 PBAPS Continued 6.2.2 Facility Staff The facility organization shall be subject to the following:

a. Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2.1, except that the shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

b. At least one licensed operator shall be in the control room and assigned to each reactor that contains fuel,

c. At least two licensed operators, excluding the operator on the second unit, shall be present in the control room during reactor ,

startup, scheduled reactor shutdown and during recovery from reactor trips.

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

e. All CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent respon-sibility during this operation.

f. Deleted,

g. In addition to the requirements of 6.2.2.a, the following shall ,

hold a senior reactor operator license: 1) Plant Manager or i Superintendent-Operations, 2) Assistant Superintendent-Operations and 3) Superintendent-Technical or Engineer-Systens. ,

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Unit 2 PBAPS 6.3 Facility Staff Oualifications 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1 - 1971 for comparable positions, except for (1) Senior - Health Physicist (radiation protection manager) who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 and (2) the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific .

training in plant design, and response and analysis _ of the plant for transients and accidents. ,

6.4 Trainina 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Superintendent-Training and shall meet the requirements of Section 5.5 of ANSI N18.1-1971 and 10 CFR 55, Appendix A. .

6.4.2 Deleted.

6.5 Review and Audit 6.5.1 Plant Operations Review Committee (PORG1 6.5.1.1 Function The Plant Operations Review Committee shall function to advise the Plant Manager on all matters related to nuclear safety.

6.5.1.2 Composition t

The Plant Operations Review Committee shall be composed of the:

Superintendent - Operations (Chairman)

Superintendent - Technical j Superintendent - Maintenance / Instrumentation and Controls l Superintendent - Plant Services i Assistant Superintendent - Operations l Maintenance Engineer i Engineer-Systems -l Regulatory Engineer l Shift Manager l l

6.5.1.3 Alternates Alternate members shall be appointed in writing by the PORC Chairman to  !

serve on a temporary basis; however, no more than two alternate members j shall be used to satisfy a PORC quorum (See 6.5.1.5).

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PBAPS 6.3 Facility Staff Oualifications 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1 - 1971 for comparable positions, except for (1) Senior - Health Physicist (radiation protection manager) who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 and (2) the Shift Technical Advisor who shall have a bachelor's' degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.

'6.4 Trainina 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Superintendent-Training and shall meet the requirements of Section 5.5 of ANSI N18.1-1971 and 10 CFR 55, Appendix A. ,

6.4.2 Deleted.

6.5 Review and Audit 6.5.1 Plant Ooerations Review Committee (PORC) 6.5.1.1 Function The Plant Operations Review Committee shall function to advise the Plant Manager on all matters related to nuclear safety.

6.5.1.2 Compositti n The Plant Operations Review Committee shall be composed of the:

Superintendent - Operations (Chairman)

Superintendent - Technical l Superintendent - Maintenance / Instrumentation and Controls l Superintendent - Plant Services Assistant Superintendent - Operations  ;

Maintenance Engineer Engineer-Systems Regulatory Engineer i Shift Manager 6.5.1.3 Alternates Alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more than two alternate members shall be used to satisfy a PORC quorum (See 6.5.1.5).

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Unit 2 PBAPS 6.5.1.6 Continue;

i. Revie', of the Plant Security Plan, and shall submit recommended charges to the Plan to the Plant Manger and the Nuclear Review Board.

J. Review of the Emergency Plan, and shall submit recommended changes to the Plan to the Plant Manager and the Nuclear Review Board.

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 plant records.

1. Review of the facility Fire Protection Program, and shall submit recommended changes to the Program to the Plant Manager and the Nuclear Review Board.

Authority 6.5.1.7 The Plant Operations Review Committee shall:

a. Recommend in writing, to the Plant Manager, for his approval or disapproval of items considered under 6.5.1.6(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 constitutes an unreviewed safety question, as defined in 10 CFR 50.59.

c. Provide immediate written notification to the Vice President, Peach Bottom Atomic Power Station, or in his absence, the Senior 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 disagreement pursuant to 6.1.1 above.

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Unit 3 PBAPS 6.5.1.6 Continued

i. Review of the Plant Security Plan, and shall submit recommended changes to the Plan to the Plant Manger and the Nuclear Review Board.

j. Review of the Emergency Plan, and shall submit recommended changes to the Plan to the Plant Manager and the Nuclear Review Board.

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 plant records.

1. Review of the facility Fire Protection Program, and shall submit recommended changes to the Program to the Plant Manager and the Nuclear Review Board.

authority 6.5.1.7 The Plant Operations Review Committee shall:

a. Recommend in writing, to the Plant Manager, for his approval or disapproval of items considered under 6.5.1.6(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 constitutes an unreviewed safety question, as defined in 10 CFR 50.59.

c. Provide immediate written notification to the Vice President, Peach Bottom Atomic Power Station, or in his absence, the Senior 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 disagreement pursuant to 6.1.1 above.

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. Unit 2 PBAPS 6.5.2.8 Continued

e. The Facility Emergency Plan and implementing procedures at j least once per year. l

f. The Facility Security Plan and implementing procedures at least once per two years.

g. The Offsite Dose Calculation Manual and implementing procedures at least once per two years.

h. The performance of activities required by the Quality Assurance Program regarding the radiological monitoring program to meet the provisions of Regulatory Guide 4.1, Revision 1, April 1975, at least once per calendar year.

i. Any other area of facility operation considered appropriate by the NRB or the Executive Vice President - Nuclear.

J. The facility Fire Protection Program and implementing procedures at least once per two years.

Authority 6.5.2.9 The NRB shall report to and advise the Executive Vice President -

Nuclear on those areas of responsibility specified in Section 6.5.2.7 and 6.5.2.8.

Records 6.5.2.10 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 10 working days following each meeting.

b. Reports of reviews encompassed by Section 6.5.2.7.e, f, g, [

and h above shall be prepared, approved and forwarded to the Executive Vice President - Nuclear, within 10 working days following completion of the review. _

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. Unit 3 PBAPS 6.5.2.8 Continued

e. The Facility Emergency Plan and implementing procedures at least once per year.

f. The Facility Security Plan and implementing procedures at.

least once per two years.

9 The Offsite Dose Calculation Manual and implementing procedures at least once per two years,

h. The performance of activities required by the Quality '

Assurance Program regarding the radiological monitoring program to meet the provisions of Regulatory Guide 4.1, Revision 1, April 1975, at least once per calendar year.

i. Any other area of facility-operation considered appropriate by the NRB or the Executive Vice President - Nuclear.

J. The facility Fire Protection Program and implementing procedures at least once per two years.

Authority 6.5.2.9 The NRB shall report to and advise the Executive Vice President -

Nuclear on those areas of responsibility specified in Section 6.5.2.7 and 6.5.2.8.

Records 6.5.2.10 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 10 working days following each meeting.

b. Reports of reviews encompassed by Section 6.5.2.7.e, f, g, and h above shall be prepared, approved and forwarded to the Executive Vice President - Nuclear, within 10 working days following completion of the review.

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6.6 Reportable 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 'l Section 50.73 to 10 CFR 50. '

b. Each Reportable Event Report submitted to the Commission shall be I l reviewed by the PORC and submitted to the NRB and the Vice President, l Peach Bottom Atomic Power Station.

6.7 Safety limit Violation l

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. 6.7.1 The following actions shall be taken in the event a Safety Limit is l l violated:

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

b. The NRC Operations Center shall be notified by telephone as soon as l possible and in all cases within I hour. The Vice President, Peach Bottom Atomic Power Station, Plant Manger, 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 I action taken to prevent recurrence. l

d. The Safety Limit Violation Report shall be submitted to the Commission, the NRB and the Vice President, Peach Bottom Atomic Power Station l .- 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, 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

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.

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d. Procedures for the implementation of the Fire Protection Program.

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. Unit 3 PBAPS 6.6 Reoortable Event ActiQD 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 Commission shall be j reviewed by the PORC and submitted to the NRB and the Vice President, i Peach Bottom Atomic Power Station. l i

6.7 Safety Limit Violation I l

6.7.1 The following actions shall be taken in the event a Safety Limit is I violated: )

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

b. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within I hour. The Vice President, Peach Bottom Atomic Power Station, Plant Manger, 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 Commission, 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, 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

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. .l

d. Procedures for the implementation of the Fire Protection Program.

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