ML20065M250

Proposed Tech Specs,Correcting Typo in Unit 3 Ts,Reflecting Name Change of PECO to PECO Energy Co & Implementing line- Item TS Improvements Recommended by GL-93-05

ML20065M250
Person / Time
Site:	Peach Bottom
Issue date:	04/15/1994
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20065M248	List: ML20065M244 ML20065M250
References
GL-93-05, GL-93-5, NUDOCS 9404250137
Download: ML20065M250 (20)

Text

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Unit 2 1 ,

PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3 REACTIVITY CONTROL 4.3 REACTIVITY CONTROL Aoolicability: Applicability:

Applies to the operational Applies to the surveillance status of the control rod requirements of the control system. rod system.

Ob.iective: Qb.iective:

To assure the ability of the To verify the ability of the control rod system to control rod system to control reactivity. control reactivity.

Specification: Specificatiqa:

A. Reactivity Limitations A. Reactivity limitations

1. Reactivity marain - 1. Reactivity marain -

core loadina core loadina A sufficient number of control Sufficient control rods shall rods shall be operable so be withdrawn following a that the core could be made refueling outage when core subcritical in the most alterations were performed to reactive condition during the demonstrate with a margin of operating cycle with the 0.38h k/k that the core can strongest control rod fully be made subcritical at any withdrawn and all other time in the subsequent fuel operable control rods fully cycle with the analytically inserted. determined strongest operable control rod fully withdrawn and all other operable rods fully inserted.

2. Reactivity marain - 2. Reactivity marain - l inoperable control rod _s. inoperable control rods I

a. Control rods which cannot a. Each partially or fully I be moved with control rod withdrawn operable control drive pressure shall be rod shall be exercised one considered inoperable. notch at least once each l week when operating above l If a partially or fully the RWM low power setpoint. l withdrawn control rod drive Each partially or fully cannot be moved with drive withdrawn operable control or scram pressure the rod shall be exercised at reactor shall be brought i least one notch within 24 to a shutdown condition hours when operating above within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> unless the RWM low power setpoint I if there are three 9404250137 940415 7 PDR ADOCK 0500

i . Unit 2  ;

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PBAPS l

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.4 STANOBY LIOUID CONTROL SYSTEM 4.4 STANDBY LIOUID CONTROL SYSTEM (Cont'd) (Cont'd)

2. Manually initiate one of the Standby Liquid Control System Pumps and pump demineralized water into the reactor vessel from the test tank.

This test checks explosion of the charge associated with the tested loop, proper operation of the explosive valves, and pump operability. The replacement charge for the explosive valve shall be from the same manufactured batch as the one fired or from another batch which has been certified by having one of the batch successfully fired.

3. Both systems, including both explosive valves, shall be tested in the course of two operating cycles.

B. Normal Systgm Reauirements B. Normal System Reauirements At all times when the Standby Liquid Control System is required to be operable, the following conditions shall be met:

1. At least 162.7 lbm Boron-10 1. Boron-10 Quantity: At least once must be stored in the Standby per month calculate and record Liquid Control Solution Tank the quantity of Boron-10 stored and be available for injection. in the Standby Liquid Control Solution Tank.

2. The sodium pentaborate 2. Concentration: At least once solution concentration must per month check and record.

be equal to or less than Also, check concentration 9.82% weight. anytime water or boron is added to the solution.

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Unit 2 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.4 STANDBY LIOUID CONTROL SYSTEM 4.4 STANDBY LIOVID CONTROL SYSTEM (Cont'd) (Cont'd)

3. The Standby Liquid Control System conditions must satisfy the following equation:

f C [j I 0 [ E %1 i

(13%wt.f(86gpmj[( 19.8% atomj where, C- Sodium Pentaborate Solution Concentration (% weight)

Q= Pump Flow Rate (gpm) 3. Pump Flow Rate: At least against a system head of l once per 92 days each pump IE25 psig. loop shall be functionally tested by pumping boron solution to the test tank.

At least once per quarter check and record pump flow rata against a system head of 1225 psig.

E= Boron-10 Enrichment (% atom 4. Enrichment: Following each Boron-10) addition of boron to the  :

solution tank, calculate enrichment within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Verify results by analysis j within 30 days. <

5. Solution Volume: At least '

once per day check and record. )

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4 Unit 2 PBAPS 6.5.2 Ruclear Review Board function 6.5.2.1 The Nuclear Review Board provide independent review (NRB) shall function to activities in the area of: and audit of designated

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

h. quality assurance practices j

! The members of the NR8 will be ncompetent the i

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! of the Quality Assurance requirements of 10 CFR 50, Appendix 8.

j Additionally, they will be i cognizant of the corporate Quality Assurance Program and will have the corporate Quality Assurance organization available to them .

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i Organization j

t 6.5.2.2 The C5' airman shall be appo,inted in writing by President - Nuclear ce the Executive Vimember in an en addition,gineering or, physical science field and inand shall hav experience, of which a minimum in one or more areas given in 6.5.2.1 a be of three years sh lls are PECO Energy CompanyThe PECO NRB shall be composed of at l e members who two outside members who a(re yees. no)t PECO emploemployees and at lea I

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Unit 2 PBAPS 6.5.2 [Lqclear Review Board Function 6.5.2.1 The Nuclear Review Board (NRB) shall function to provide independent review and audit of designated activities in the area 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

h. quality assurance practices The members of the NRB will be competent in the area of quality assurance practice and cognizant of the Quality Assurance requirements of 10 CFR 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.

Oraanization 6.5.2.2 The Chairman, members and alternate members of the NRB shall be appointed in writing by the Executive Vice President - Nuclear, and shall have an academic degree in an engineering or physical science field and in addition, shall have a minimum of five years +.echnical experience, of which a minimum of three yeari shall be in one or more areas given in 6.5.2.1.

The NRB shall be composed of at least five members who are PECO Energy Company (PECO) employees and at least two outside members who are not PECO employees.

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• Unit 2 PBAPS-

'6.9.1 Routine Reports (cont'd)

c. Annual Safetv/ Relief Valve Repor1 Describe all challenges to the primary coolant system safety and relief valves. Challenges are defined as the automatic opening of the primary coolant safety or relief valves in response to high reactor pressure,

d. Monthly Doeratina Report Routine reports of operating statistics and shutdown experience and a narrative summary of the operating experience shall be submitted on a monthly basis. Each report shall be submitted no later than the 15th of the month following the calendar month covered by the report.

e. Core Ooeratino Limits Report (1) Core operating limits shall be established and shall be documented in the CORE OPERATING LIMITS REPORT prior to each Operating Cycle, or prior to any remaining portion of an Operating Cycle, for the following:

a. The APLHGR for Specification 3.5.I,

b. The MCPR for Specification 3.5.K,

c. The core flow and power adjustment factors for Specification 3.5.K and 3.5.I,  ;

d. The LHGR for Specification 3.5.J,

e. The upscale power biased Rod Block Monitor setpoints and corresponding power levels.

(2) The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents as amended and  !

approved l

a. NEDE-240ll-P-A, " General Electric Standard Application for Reactor Fuel" (latest approved version)

b. " Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Peach Bottom  :

Atomic Power Station Units 2 and 3," NEDC- i 32162P, Revision 1, February, 1993 l l

c. PECO Energy Company Methodologies as described l l in:

(1) PECo-FMS-0001-A, " Steady-State Thermal Hydraulic Analysis of Peach Bottom Units 2 and 3 using the FIBWR Computer Code"

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Unit 2 PBAPS 6.0 Environmental Surveillance and Special Study Proarams Studies described in this section will be terminated upon agreement by PECO Energy Company and the Nuclear Regulatory Commission that the intended purpose of the study has been satisfied.

6.1 (Deleted) 6.2 (Deleted) 6.3 (Deleted) l l

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Note: Pages 15-47 l have been deleted.

The next page is 48. l

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UNITED STATES A704IC ENERGY CWMISSION Washington, DC 20545 PECD FNEffiY OEPANY IUBLIC SERVICE EIECTRIC AND CAS COMPANY DEI 14ARVA IMER AND LIGff OCMPANY ATIMPIC CITY EIECTRIC CCNPANY DOCIGP NO. 50-278 PFAW BCTPIU4 ATOMIC IWER STATION, UNIT 3 FACILITY OPERATDK; LICENSE License No. DPR-56

1. 7he Atomic Energy Commission (the armtission) haviry found that:

A. The application for license filed by PEOO Energy Campany, formerly Philadelphia Electric Campany, Public Service Electric and Gas Company, Delmarva Power and Light Campany, and Atlantic City Electric Company (the licensees) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I and all required notifications to other agencies or bodies have been duly made; B. Construction of the Peach Bottom Atomic Power Station, Unit 3 (the facility) has been substantially completed in conformity with Construction Permit No.

CPPR-38 and the application, as amended, the provisions of the Act aM the rules and regulations of the CW,minnion; C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Cammission; D. 7here is reasonable assurance: (1) that the activities authorized by this operating license can be coMucted without endangerirg the health and safety of the public, and (2) that such activities will be coMucted in ccrnpliance with the rules aM regulations of the Commission; E. PECD Energy Company is technically qualified and the licensees are financially qualified to engage in the activities authorized by this amended operatiry license in accordance with the rules and regulations of the Commission; F. The licensees have satisfied the applicable provisions of 10 CFR Part 140,

" Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; G. The issuance of this operating license will not be inimical to the coman defense and security or to the health and safety of the public; Page 1

H. After weighing the environmental, econcanic, technical, and other benefits of the facility against environmental costs and considering available alternatives, the issuance of Facility Operating License No. DPR-56 is in accordance with 10 CFR Part 50, Apperdix D, of the Camission's regulations  ;

ard all applicable requirements of said Appendix D have been satisfied; and i I. The receipt, possession, and use of by-product and special nuclear material as authorized by this license will be in accordance with the Ctannission's regulations in 10 CFR Parts 30, 40, and 70, including 10 CFR Section 30.33, 40.32, and 70.23 and 70.31.

2. Facility Operating License No. DPR-56 is hereby issued to the PECO Energy Octnparry, formerly the Ihiladelphia Electric Campany, Public Service Electric and Gas Ocarpany (PSE&G), Delmarva Power and Light Campany (DP&IC), and Atlantic City Electric Campany (ACEC), is hereby amended in its entirety to read as follows:

A. This license applies to the Peach Bottcra Atamic Power Station, Unit 3, a direct cycle, forced cirud stion, boiling water nuclear reactor and associated equipment (the facility), owned by the licensees and operated by PEOO Energy Ocrpany. The facility is located in Peach Bottam, York County, Pennsylvania ard is described in the " Final Safety Analysis Report" as supplemented and amerded (Amendments 1 through 31) and the Environmental Report as supplemented and amended (Supplements 1 through 6) .

B. Subject to the conditions ard requirements incorporated herein, the Cammission hereby licenses: l (1) PECO Energy Campany, pursuant to Section 104b of the Act and 10 CFR Part 50, " Licensing of Production and Utilization Facilities," to possess, use, and operate the facility and PSE&G, DP&If, and ACEC to pmeen the facility at the designated location in Ibach Bottam, York County, ,

Pennsylvania in accordance with the procedures and limitations set forth in this license; (2) PEOO Energy Company, pursuant to the Act ard 10 CFR Part 70, to receive, l Immen and use at any time special nuclear material as reactor fuel, in i accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended, as of December 15, 1975; (3) PECD Energy Campany, pursuant to the Act and 10 CFR Parts 30, 40, and 70 I to receive, pnnenn and use at any time any byproduct, source and l special nuclear material as sealed neutron sources for reactor startup, i sealed sources for reactor instrumentation ard radiation monitority equipment calibration, ard as fission detectors in amounts as required; (4) PECD Energy Campany, pursuant to the Act and 10 CFR Parts 30, 40 ard 70 to receive, possess and use in amounts as required any byproduct, i em, or special nuclear material without restriction to chmb1 or physical form for sample analysis or instrument calibration or when associated with radioactive apparatus or camponents; Page 2

a (5) PE00 Energy Ocupany, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility.

C. This license shall be docmed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part.

20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Canaission now or hereafter in effect; and is subject to the additional conditions specified below:

(1) Maximum Ibwer Level PEOO Energy Campany is authorized to operate the Peach Bottcn Atomic Power Station, Unit 3, at steady state reactor core power levels not to exceed 3293 megawatts thermal.

(2) Technical Specifications

'Ihe Technical Specifications contained in Appendices A arxl B, as revised through Amendment No. are hereby incorporated in the license. PECO Energy Campany shall operate the facility in accordance with the Technical Specifications.

(3) Fhysical Protection

'1he licensee shall fully implement and maintain in effect all provisions of the (Ymimion-approved physical security, guarti training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). 'Ihe plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: " Peach Bottom Atcalc Power Station, Units 2' and 3, Ehysical Security Plan," with revisions submitted through December 16, 1987;

" Peach Bottom Atomic Power Station, Units 2 and 3 Plant Security Personnel Training and Qualification Plan," with revisions submitted' through July 9,1986; and " Peach Bottcn Atomic Power Station, Units 2 and 3 Safeguards Contingency Plan," with revisions submitted through March 10, 1981. 01anges made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

(4) 'Ihe licensee may proceed with and is required to cxanplete the modifications identified in Paragraphs 3.1.1 through 3.1.16 of the NRC's Fire Protection Safety Evaluation (SE), dated May 23, 1979 for the facility. 'Ihese modifications will be cmpleted in accordance with the schedule in Table 3.1 of the SE and supplements thereto. In addition, the licensee shall submit the additional information identified in Table 3.2 of this SE in accordance with the schedule contained therein.

O Page 3

(5) Operation beyond the end-of-cycle (all rods out cordition) thermal pweris limited to seventy (70) percent mininn. Increasing core pwer ,

level via reduced feedwater heating, once operation in the coastdown l node has begun, is not permitted unless the licensee has performed and analysis of this cperating condition that confirms that this condition is bounded by the analysis for the particular cycle of operation. l

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

l A. If the actual milk sample measurements taken at the nearby farms in accordance l with the Technical Specifications, predict a dose to a child's thyroid, based  ;

on actual cmbined operation of Unit 2 ard 3, that exceeds 15 mrenVyear, licensees shall install for operation no later than the next refueling cycle i for each unit the r==ry equipnent to reduce the projected dose to such l levels. I B. To the extent matters related to thermal discharges are treated therein, operation of Peach Bottom Atomic Ibwer Station Unit 2 will be governed by NPDES Permit No. PA 0009733, as now in effect and as hereafter amended.

Questions pertainity to conformance thereto shall be referred to and shall be )

determined by the NPDES Permit issuing or enforcement authority, as appropriate.

C. In the event of any nodification of the NPDES Permit related to thermal discharges or the establistunent (or amendment) of alternative effluent i limitations established pursuant to Section 316 of the Federal Water Pollution i Control Act, the licensees shall inform the NRC and analyze any associated  !

changes in or to the Station, its components, its operation or in the l discharge of effluents therefrcan. If such charge would entail any modification to this license, or any technical specifications which are part of this license, or present an unreviewed safety question or involve an envirorumntal impact different than analyzed in the Final Environmental Statement, the licensees shall file with the NRC, as applicable, an appropriate analysis of any such charge on facility safety, and/or an analysis i of any such change on the environmental impacts and on the overallcost-benefit )

balance for facility operation set forth in the Final Environmental Statement j and a request for an amendment to the operating license, if required by the -l Commission's regulations. As used in this Cordition 3. (d), Final  !

Environmental Statement means the NRC Staff Final Environmental Statement related to Operation of Peach Bottom Atomic Power Station Units Nos. 2 and 3 dated April 1973, as modified by (1) the Initial Decision of the Atomic Safety  !

ard Licensity Board dated September 14, 1973, (2) the Supplemental Initial 1 Decision of the Atomic Safety and Licensing Board dated June 14, 1974, (3) the Decision of the Atomic Safety and Licensing Appeal Board dated July 5,1974, (4) the Memorandum and Order of the rhmm b ian dated August 8, 1974, (5) any i further modification resultirg from further review by the Appeal Board ard by  ;

the Commission, if any, ard (6) any Environmertal Impact Appraisal which has I been or may be issued by the NRC since the FES was published in April 1973.

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4. This license is effective as the date of issuance and shall expire at midnight on July 2, 2014.

FOR 11E ATQ4IC DERGY CuiMISSION Original Signed by Ibger Boyd, for A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing Attachments:

Amended pages to Apperrlices A and B DIR-44 & DTR-56 Technical Specifications Date of Issuance: July 2, 1974 l

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• Unit 3 4 .

PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3 REACTIVITY CONTROL 4.3 REACTIVITY CONTROL Acolicability: Applicability:

Applies to the operational Applies to the surveillance status of the control rod requirements of the control system, rod system.

Ob.iective: Obiective:

To assure the ability of the To verify the ability of the control rod system to control rod system to control reactivity. control reactivity.

Soecification: Specification:

A. Reactivity Limitations A. Reactivity Limitations

1. Reactivity marain - 1. Reactivity marain -

core loadina core loadina A sufficient number of control Sufficient control rods shall rods shall be operable so be withdrawn following a that the core could be made refueling outage when core subcritical in the most alterations were performed to reactive condition during the demonstrate with a margin of operating cycle with the 0.38hk/k that the core can strongest control rod fully be made subcritical at any withdrawn and all other time in the subsequent fuel operable control rods fully cycle with the analytically inserted. determined strongest operable control rod fully withdrawn and all other operable rods fully inserted.

2. Reactivity marain - 2. Reactivity marain -

inocerable control rods inoperable control rods

a. Control rods which cannot a. Each partially or fully be moved with control rod withdrawn operable control drive pressure shall be rod shall be exercised one considered inoperable. notch at least once each week when operating above If a partially or fully the RWM low power setpoint.

withdrawn control rod drive Each partially or fully cannot be moved with drive withdrawn operable control or scram pressure the rod shall be exercised at reactor shall be brought I least one notch within 24 to a shutdown condition hours when operating above within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> unless the RWM low power setpoint if there are three Unit 3 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3.A Reactivity limitations 4.3.A Reactivity limitations (Cont'd) (Cont'd)

f. Inoperable control rods shall be positioned such that specification 3.3.A.1 is met. In addition, during reactor power operation, no more than one control rod in any 5 x 5 array may l be inoperable (at least 4 operable control rods must separate any 2 inoperable ones). If this Specification cannot be met the reactor shall not be started, or if at power, the reactor shall be brought to a cold shutdown ,

condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

B. Control Rods

1. Each control rod shall be B. Control Rods coupled to its drive or completely inserted and the 1. The coupling integrity shall control rod directional be verified for each withdrawn control valves disarmed control rod as follows:

electrically except as in 3.3.B.1.a. This requirement a. When a rod is withdrawn ,

does not apply in the refuel the first time after each condition when the reactor refueling outage or after is vented. Two control maintenance, observe discernible rod drives may be removed response of the nuclear as long as Specification 3.3.A.1 instrumentation and rod is met. position indication for the " full-in" and " full-out"

a. For control rod 54-35, for position. However, for initial the remainder of cycle 10 (to rods when response is not be completed before 10/30/95). discernible, subsequent i exercising of these rods after '

If coupling cannot be the reactor is above the Rod Worth i accomplished, the uncoupled control Minimizer low power setpoint rod may be withdrawn when 210% shall be performed to verify of rated thermal power instrumentation response, i only if all the following conditions are satisfied: b. When the rod is fully withdrawn the first time

1) no other uncoupled control after each refueling outage rod is withdrawn; or after maintenance observe that the drive does not go

2) the uncoupled control rod to the overtravel position.

may not be withdrawn past notch position 46.

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., Unit 3 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.4 STANDBY LIOUID CONTROL SYSTEM 4.4 STANDBY LIOUID CONTROL SYSTEM (Cont'd) (Cont'd)

2. Manually initiate one of the Standby Liquid Control System Pumps and pump demineralized water into the reactor vessel from the test tank.

This test checks explosion of the charge associated with the tested loop, proper operation of the explosive valves, and pump operability. The replacement charge for the explosive valve shall be from the same manufactured batch as the one fired or from another batch which has been certified by having one of the batch successfully fired.

3. Both systems, including both explosive valves, shall be tested in the course of two operating cycles.

B. Normal System Reauirements B. Normal SystegLReauirements At all times when the Standby Liquid Control System is required to be operable, the following conditions shall be met:

1. At least 162.7 lbm Baron-10 1. Boron-10 Quantity: At least once must be stored in the Standby per month calculate and record Liquid Control Solution Tank the quantity of Boron-10 stored and be available for injection. in the Standby Liquid Control Suiution Tank.

2. The sodium pentaborate 2. Concentration: At least once solution concentration must per month check and record.

be equal to or less than Also, check concentration 9.82% weight. anytime water or boron is added to the solution.

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e Unit 3 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.4 STANDBY LIQUID CONTROL SYSTEM 4.4 SIMDS1 LIOUID CONTROL SYSTEM (Cont'd) (Cont'd)

3. The Standby Liquid Control System conditions must satisfy the following equation:

I C (( 0 [

(13%wt.j'(86gpmf{19.8%atomj E I>l where, C- Sodium Pentaborate Solution Concentration (% weight)

Q= Pump Flow Rate (gpm) 3. Pump Flow Rate: At least against a system head of j once per 92 days each pump 1225 psig. loop shall be functionally tested by pumping boron solution to the test tank.

At least once per quarter check and record pump flow rate against a system head of 1225 psig.

E- Boron-10 Enrichment (% atom 4. Enrichment: Following each Boron-10) addition of boron to the solution tank, calculate enrichment within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Verify results by analysis within 30 days.

5. Solution Volume: At least i once per day check and record.

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Unit 3 PBAPS 6.5.2 Nuclear Review Board function 6.5.2.1 The Nuclear Review Board (NRB) shall function to provide independent review and audit of designated activities in the area 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

h. quality assurance practices The members cf the NRB will be competent in the area of quality assurance practice and cognizant of the Quality Assurance requirements of 10 CFR 50, Appendix B. Additionally, they will be cognizant of the corporate Quality Asxfrance Program and will have the corporate Quality Assurance organization available to them.

Oraanization 6.5.2.2 The Chairman, members and alternate members of the NRB shall be appointed in writing by the Executive Vice President - Nuclear, and shall have an academic degree in an engineering or physical science field and in addition, shall have a minimum of five years technical experience, of which a minimum of three years shall be in one or more areas given in 6.5.2.1.

The NRB shall be composed of at least five members who are PECO Energy Company (PECO) employees and at least two outside members who are not PECO employees.

i l

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o*'* pggp3 Unit 3 i

6.9.1 Routine Reports (cont'd) l

c. Annual Safetv/ Relief Valve Report .

Describe all challenges to the primary coolant system j safety and relief valves. Challenges are defined as the ,

automatic opening of the primary coolant safety or i relief valves in response to high reactor pressure.

d. Monthly Operatina Rep _qt.t Routine reports of operating statistics and shutdown experience and a narrative summary of the operating experience shall be submitted on a monthly basis. Each report shall be submitted no later than the 15th of the month following the calendar month covered by the report.

e. Core Operatina limits Report (1) Core operating limits shall be established and shall be documented in the CORE OPERATING LIMITS REPORT prior to each Operating Cycle, or prior to any remaining portion of an Operating Cycle, for the following:

a. The APLHGR for Specification 3.5.I,

b. The MCPR for Specification 3.5.K,

c. The core flow and power adjustment factors for Specification 3.5.K and 3.5.I,

d. The LHGR for Specification 3.5.J,

e. The upscale power biased Rod Block Monitor setpoints and corresponding power levels.

(2) The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents as amended and approved:

a. NEDE-24011-P-A, " General Electric Standard Application for Reactor Fuel" (latest approved version)

b. " Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Peach Bottom Atomic Power Station Units E and 3," NEDC-32162P, Revision 1, February, 1993

c. PECO Energy Company Methodologies as described l .

l in-(1) PEco-FMS-0001-A, " Steady-State Thermal i Hydraulic Analysis of Peach Bottom 1 Units 2 and 3 using the FIBWR Computer Code"

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Unit 3 PBAPS 6.0 Epvironmental Surveillance and Special Study Procrami Studies described in this section will be terminated upon agreement by PECO Energy Company and the Nuclear Regulatory Commission i ,

that the intended purpose of the study has been satisfied.

6.1 (Deleted) 6.2 (Deleted) 6.3 (Deleted)

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