ML20094N169

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Amends 104 & 68 to Licenses NPF-39 & NPF-85,respectively, Changing Fire Protection License Condition & Relocate Fire Protection TS Requirements to Update Final Safety Analysis Rept IAW GL 86-10 & GL 88-12
ML20094N169
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 11/20/1995
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Philadelphia Electric Co
Shared Package
ML20094N172 List:
References
NPF-39-A-104, NPF-85-A-068, GL-86-010, GL-88-012 NUDOCS 9511270401
Download: ML20094N169 (31)
v • d • e


Text

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,h UNITED STATES g

j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20eeH001 i

PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-352 LIMERICK GENERATING STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 104 License No. NPF-39 1.

The Nuclear Regulatory Comission (the Commission) has found that:

A.

The application for amendment by Philadelphia Electric Company (the licensee) dated December 2, 1994, at supplemented May 12, 1995, 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; j

B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

9511270401 951120 PDR ADOCK 05000352 P

PDR

.. I 2.

Accordingly, Facility Operating License No. NPF-39, paragraph 2.C.(3) is hereby amended to read as follows:

Fire Protection (Section 9.5. SSER-2.-4)*

a.

. Philadelphia Electric 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 August 1983 thru Supplement 9, dated August 1989, and Safety Evaluation dated November 20, 1995, subject to the following provision:

The licensee 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 i

in the event of a fire.

3.

Further, the license is amended by changes to the Technical Specifications i

as indicated in the attachment to this license amendment, and paragraph :

2.C.(2) of Facility Operating License No. NPF-39 is hereby amended to read as follows:

4 Technical Snecifications i

The Technical Specifications contained in Appendix A and the Environmental l

Protection. Plan contained in Appendix B, as revised through Amendment No.

104, are hereby incorporated into this license.

Philadelphia Electric l

Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

4.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY C0fMISSION

. Stolz, Director ect Directorate I-2 vision of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachments: 1.

Page 4 of License

  • 2.

Changes to the Technical Specifications Date of Issuance:

November 20, 1995

  • Page 4 is attached, for convenience, for the composite license to reflect this change.

l.

ATTACHMENT TO LICENSE AMENDMENT NO. 104 FACILITY OPERATING LICENSE NO. NPF-39 l.

l DOCKET NO. 50-352 Replace the following pages of the Facility Operating License (FOL), and the Appendix A Technical Specificat. ions with the attached pages. The revised l

pages_ are identified by Amendment number and contain vertical lines indicating the area of change.

Et9"!Jt Insert FOL 4

4 Appendix A ix ix xiv xiv xix xix

+

xxi xxi 3/4 3-92 3/4 3-92 3/4 3-93 3/4 3-94 3/4 3-95 3/4 3-96 3/4 7-19 3/4 7-19 3/4 7-20 3/4 7-21 3/4 7-22 3/4 7-23 3/4 7-24 3/4 7-25 3/4 7-26 3/4 7-27 3/4 7-28 3/4 7-29 3/4 7-30 3/4 7-31 3/4 7-32 B 3/4 3-6 8 3/4 3-6 B 3/4 3-7 8 3/4 3-7 B 3/4 7-4 8 3/4 7-4 6-2 6-2 6-8 6-8

_. ~ _ _ _ _ _. _

t i

. (3) Fire Protection (Section 9.5. SSER-2.-4)*

Philadelphia Electric 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 August 1983 through Supplement 9, dated August 1989, and Safety Evaluation dated November 20, 1995, subject to the following provision:

The licensee 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.

I i

I

  • The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.

LIMERICK - UNIT I Amendment No. 104

i t

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION Egg

]

INSTRUMENTATION (Continued)

Table 4.3.7.1-1 Radiation ;ionitoring i

Instrumentation Surveillance Requirements..............................

3/4 3-66 The information from pages 3/4 3-68 through 3/4 3-72 has been intentionally omitted. Refer to note on page 3/4 3-68..................

  • 3/4 3-68 The information from pages 3/4 3-73 through 3/4 3-75 has been intentionally l

omitted. Refer to note on page 3/4 3-73..................

3/4 3-73 i

Remote Shutdown System Instrumentation and Control s.............

3/4 3-76 i

Table 3.3.7.4-1 Remote Shutdown System 4

Instrumentation and Controls................

3/4 3-77 Table 4.3.7.4-1 Remote Shutdown System i

Instrumentation Surveillance i

Requirements..............................

3/4 3-83

'ccident' Monitoring Instrumentation.............................

3/4 3-84 A

Table 3.3.7.5-1 Accident Monitoring Instrumen-l tation....................................

3/4 3-85 i

Table 4.3.7.5-1 Accidant Monitoring Instrumenta-i tion Serveillance Requirements............

3/4 3-87 Source Range Monitors...........................................

3/4 3-88 i

Traveraing In-Core Probe System.................................

3/4 3-89 i

i Chl o ri ne Detecti on Sys tem.......................................

3/4 3-90 Toxic Gas Detection System......................................

3/4 3-91 DELETED; Refer to note on page..................................

3/4 3-92 i

LIMERICK - UNIT 1 ix Amendment No. 48,75,104

-. ~..

INDil LINITING ColeITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION EAgg PLANT SYSTEMS (Continued) 3/4.7.2 CONTROL ROOM EMERGENCY FRESH AIR SUPPLY SYSTEM - C0fMON SYSTEM.................................................

3/4 7-6 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM..................

3/4 7-9 3/4.7.4 SNUB 8ERS..............................................'.

3/4 7-11 Figure 4.7.4-1 Sample Plan 2) For Snubber Functional Test...................

3/4 7-16 3/4.7.5 SEALED SOURCE CONTAMINATION............................

3/4 7-17 3/4.7.6 DELETED; Refer to note on page.........................

3/4 7-19 3/4.7.7 DELETED; Refer to note on page.........................

3/4 7-19 3/4.7.8 MAIN TURBINE BYPASS SYSTEM.............................

3/4 7-33 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES A.C. Sources - Operating...................................

3/4 8-1 Table 4.8.1.1.2-1 Diesel Generator Test Sc hed u l e..............................

3/4 8-8 A.C. Sources - Shutdown....................................

3/4 8-9 3/4.8.2 D.C. SOURCES D.C. Sources - Operating...................................

3/4 8-10 LIMERICK - UNIT 1 xiv Amendment No. 33,49,52,104

a IfiDfl BASES SECTION ggg j

INSTRUMENTATION (Continued)

(7eleted)..............................................

B 3/4 3-5 (Deleted)..............................................

B 3/4 3-5 l

Remote Shutdown System Instrumentation and Controls....

B 3/4 3-5 Accident Monitoring Instrumentation....................

  • B 3/4 3-5 Source Range Monitors..................................

B 3/4 3-5 Traversing In-Core Probe System........................

B 3/4 3-6 Chlorine and Toxic Gas Detection Systems...............

B 3/4 3-6 (Deleted)..............................................

B 3/4 3-6 Loose-Part Detection System............................

B 3/4 3-7 i

(Deleted)..............................................

B 3/4 3-7 Offgas Monitoring Instrumentation......................

B 3/4 3-7 3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM....................

B 3/4 3-7 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION i

INSTRUMENTATION........................................

B/3/4 3-7 Bases Figure B 3/4.3-1 Reactor Vessel Water Level........................

B 3/4 3-8 3/4.4.. REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM...................................

B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES...................................

B 3/4 4-2 3/4.4.3 REACTOR C0OLANT SYSTEM LEAKAGE Leakage Detection Systems...........................

B 3/4 4-3 Operational Leakage.................................

B 3/4 4-3 3/4.4.4 Cil EM I STRY...........................................

B 3/4 4-3 LIMERICK - UNIT 1 xix Amendment No. 48,53,59,75, 104

o IND.El BASES SECTION P.8E CONTAIMENT SYSTEMS (Continued) 3/4.6.3 PRIMARY CONTAIMENT ISOLATION VALVES.............

B 3/4 6-4 3/4.6.4 VACUUM RELIEF....................................

B 3/4 6-4 3/4.6.5 SECONDARY C0NTAIMENT............................

B 3/4 6-5 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL...........

B 3/4 6-6 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS - COMON SYSTEMS...........

B 3/4 7-1 3/4.7.2 CONTROL ROOM EMERGENCY FRESH AIR SUPPLY SYSTEM -

COMON SY ST EM....................................

B 3/4 7-la 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM............

B 3/4 7-la 3/4.7.4 SNUB 8ERS.........................................

B 3/4 7-2 3/4.7.5 SEALED SOURCE CONTAMINATION......................

B 3/4 7-3 3/4.7.6 (Deleted)........................................

B 3/4 7-4 3/4.7.7 (Deleted)........................................

B 3/4 7-4 3/4.7.8 MAIN TURBINE BYPASS SYSTEM.......................

B 3/4 7-5 3/4.8 ELECTRICAL POWER SYSTEM 3/4.8.1,3/4.8.2,and 3/4.8.3 A.C. SOURCES, D.C. SOURCES, AND ONSITE POWER DISTRIBUTION SYSTEMS.............................

B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES..........

B 3/4 8-3 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH..............................

B 3/4 9-1 3/4.9.2 INSTRUMENTATION..................................

B 3/4 9-1 3/4.9.3 CONTROL ROD P0SITION.............................

B 3/4 9-1 3/4.9.4 DECAY TIME.......................................

B 3/4 9-1 3/4.9.5 C0MUNICATIONS...................................

B 3/4 9-1 LIMERICK - UNIT 1 xxi Amendment No.27,40,52, 104

INSTRUMENTATION Section 3/4.7.9 (Deleted) l THE INFORMATION FROM THIS TECHNICAL SPECIFICATIONS SECTION HAS BEEN RELOCATED TO THE TECHNICAL REQUIREMENTS MANUAL (TRN) FIRE PROTECTION SECTION. TECHNICAL SPECIFICATIONS PAGES 3/4 3-92 THROUGH 3/4 3-96 0F THIS SECTION HAVE BEEN INTENTIONALLY OMITTED.

LIMERICK - UNIT 1 3/4 3-92 Amendment No. 64,104

~ _ -

PLANT SYSTEMS Section 3/4.7.6 throuah 3/4.7,7 (Deleted) i 1

THE INFORMATION FROM THESE TECHNICAL SPECIFICATIONS SECTIONS HAVE BEEN RELOCATED TO THE TECHNICAL REQUIREMENTS MANUAL (TRM) FIRE PROTECTION SECTION. TECHNICAL SPECIFICATIONS PAGES 3/4 7-19 THROUGH 3/4 7-32 HAVE BEEN INTENTIONALLY ONITTED.

)

LIMERICK - UNIT I 3/4 7-19 Amendment No. 14, 104

)

INSTRUMENTATION i

l, BASES 3/4.3.7.7' TRAVERSING IN-CORE PROBE SYSTEM The OPERA 81LITY of the traversing in-core probe system with the specified minimum complement of equipment ensures that the measurements obtained from use of this couipment accurately represent the spacial neutron flux distribution of the reactor Core.

4 i

The TIP system operability is demonstrated by normalizing all probes (i.e.,

detectors) prior to performing an LPRM calibration function. Monitoring core thermal limits may involve utilizing individual detectors to monitor selected areas of the f

t' reactor core thus all detectors may not be required to be OPERABLE. The OPERA 8ILITY of individual detectors to be used for monitoring is demonstrated by comparing the i

detector (s) output in the resultant heat balance calculation (P-1) with data obtained during a previous heat balance calculation (P-1).

l 3/4.3.7.8 CHLORINE AND T0XIC GAS DETECTION SYSTEMS i

The OPERABILITY of the chlorine and toxic gas detection systems ensures i

that an accidental chlorine and/or toxic gas release will be detected promptly j

and the necessary protective actions will be automatically. initiated for chlo-rine and manually initiated for toxic gas to provide protection for control j

room personnel. Upon detection of a high concentration of chlorine, the control room emergency ventilation system will automatically be placed in the chlorine i

isolation mode of operation to provide the required protection. Upon detection 1

of a high concentration of toxic gas, the control room emergency ventilation system will manually be placed in the chlorine isolation mode of operation to provide the required protection. The detection systems required by this s fication are consistent with the recommendations of Regulatory Guide 1.95,peci-

" Pro-taction of Nuclear Power Plant Control Room Operators against an Accidental Chlorine Release," February 1975.

There are three toxic gas detection subsystems. The high toxic chemical concentration alarm in the Main Control Room annunciates when two of the three subsystems detect a high toxic gas concentration. An Operate /Inop keylock switch is provided for each subsystem which allows an individual subsystem to be placed in the tripped condition.

Placing the keylock switch in the IN0P position initiates one of the two inputs required to initiate the alarm in the Main Control Room.

Specified surveillance intervals and maintenance outage times have been determined in accordance with GENE-770-06-1, " Bases for Changes to Surveillance Test Intervals and Allowed Out-of-service Times for Selected Instrumentation Technical Specifications," as approved by the NRC and documented in the SER (letter to R.D.

Binz, IV, from C.E. Rossi dated July 21,1992).

3/4.3.7.9 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE TRM.

LIMERICK - UNIT 1 8 3/4 3-6 Amendment No. 48,64,74,84,104 m

-em---,-

--+-m 2

-w m

l INSTRUMENTATION 1

BASES 1

l 4

3/4.3.7.10 LODSE PART DETECTION SYSTEM l

The OPERA 81LITY of the loose-part detection system ensures that sufficient capability is available to detect loose metallic parts in the primary system j

and avoid or mitigate damage to primary system components. The allowable out-of-service times and surveillance requirements are consistent with the recom-t mendations of Regulatory Guide 1.133, " Loose-Part Detection Program for the j

Primary System of Light-Water-Cooled Reactors," May 1981.

3/4.3.7.11 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE 00CM.

l 3/4.3.7.12 0FFGAS MONITORING INSTRUMENTATION This instrumentation includes provisions for monitoring the l

concentrations of potentially explosive gas mixtures and noble gases in the j

off-gas system.

4 1

3/4.3.8 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE UFSAR.

I l

3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRt3tENTATION The feedwater/ main turbine trip system actuation instrumentation is 4

provided to initiate action of the feedwater system / main turbine trip system j

in the event of failure of feedwater controller under maximum demand.

a

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i

)

l i

J LIMERICK - UNIT 1 B 3/4 3-7 AmendmentNo. 33,(8,70,100,104

~

i PLANT SYSTES BASES 3/4 7.6 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE TRM.

3/4.7.7 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE TRM.

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l LIMERICK - UNIT 1 B 3/4 7-4 Amendment No. 104

1 l

ADMINISTRATIVE CONTROLS 1'

6.2.2 UNIT STAFF

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2.2-1;
b. At least one licensed Operator shall be in the control room when fuel is in the reactor.

In addition, while the unit is in OPERATIONAL CONDITION 1, 2, or 3, at least one licensed Senior Operator shall be in the control room:

c. A Health Physics Technician
  • shall be on site when fuel.is in the-reactor;
d. ALL CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation;
e. (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE TRM.
f. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions (e.g., licensed Senior Operators, licensed Operators, health physi.

cists, auxiliary operators, and key maintenance personnel).

t Adequate shift coverage shall be maintained without routine heavy

~

use of overtime.. The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the unit is operating.

However, in the event that unforeseen problems require substantia amounts of overtime to be used, or during extended periods of shut-down for refueling, major maintenance, or major unit modifications, on a temporary basis the following guidelines shall be followed:

1. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.
2. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor 'more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all excluding shift turncver time.
3. A break of et least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work periods, including shift turnover time.
4. Except during extended shutdown periods, the use of overtime-should be considered on an individual basis and not for the entire staff on a shift.
  • The Health Physics Technician position 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, provided immediate action is taken to fill the required position.

LIMERICK - UNIT 1 6-2 Amendment No. 49,35, 96,104

ADMINISTRATIVE CONTROLS RESPONSIBILITIES 6.5.1.6 The PROC 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 50.5g 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;
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. Performance of special reviews, investigations, or analyses and reports thereon as requested by the Vice President, Limerick Generating Station, plant Manager or the Chairman of the Nuclear Review Board;
j. Review of the Security Plan and implementing procedures and submittal of recommended changes to the Nuclear Review Board; and
k. Review of the Emergency Plan and implementing procedures and submittal of the recommended changes to the Nuclear Review Board.
1. Review of every unplanned onsite release of radioactive material to the 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.
n. Review of the Fire Protection Program and implementing procedures and the submittal of recommended changes to the Nuclear Review Board.

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.

1 LIMERICK - UNIT 1 6-8 Amendment No. 40,47, 104

[partsu

  • 2 UNITED STATES j

NUCLEAR REGULATORY COMMISSION 2

WASHINGTON, D.C. 20eeMo01

\\...../

PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353 LIMERICK GENERATING STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 68 License No. NPF-85 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Philadelphia Electric Company (the licensee) dated December 2, 1994, as supplemented May 12, 1995, 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; 8.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulationr; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

~

2.

Accordingly, Facility Operating License No. NPF-85, paragraph 2.C.(3) is hereby amended to read as follows:

Fire Protection (Section 9.5. SSER-2.-4)*

Philadelphia Electric 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 August 1983 thru Supplement 9, dated August 1989, and Safety Evaluation dated November 20, 1995, subject to the following provision:

The licensee 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.

Further, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph..

2.C.(2) of Facility Operating License No. NPF-85 is hereby amended to read as follows:

Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.

68, are hereby incorporated into this license.

Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental-Protection Plan.

4.

This license amendment is e.fective as of its date of issuance and shall be implemented within 30 days.

4 FOR THE NUCLEAR REG LATORY COMISSION J n F. Stolz, Direc r roject Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachments: 1.

Pages 3 and 4 of License

  • 2.

Changes to the Technical Specifications Date of Issuance:

November 20, 1995

  • Pages 3 and 4 are attached, for convenience, for the composite license to reflect this change.

. ~.

ATTACHMENT TO LICENSE AMENDMENT NO. 68 FACILITY OPERATING LICENSE NO. NPF-85 DOCKET NO. 50-353 i

Replace the following pages of the Facility Operating License (FOL), and the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating i

the area of change.

Remove Insert FOL 3

3 4

4 Appendix A ix ix xiv xiv xix xiX xxi xxi 3/4 3-92 3/4 3-92 3/4 3-93 3/4 3-94 i

3/4 3-95 3/4 3-96 3/4 7-19 3/4 7-19 3/4 7-20 3/4 7-21 3/4 7-22 3/4 7-23 3/4 7-24 3/4 7-25 3/4 7-26 3/4 7-27 i

3/4 7-28 3/4 7-29 3/4 7-30 3/4 7-31 3/4 7-32 B 3/4 3-6 B 3/4 3-6 B 3/4 3-7 8 3/4 3-7 8 3/4 7-4 8 3/4 7-4 6-2 6-2 6-8 6-8

_3_

(4)

Pursuant to the Act and 10 CFR Parts 30, 40, 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus ~or components; and (5)

Pursuant.to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility, and to receive and possess, but not separate, such source, byproduct, and special nuclear materials as contained in the fuel assemblies and fuel channels from the Shoreham Nuclear Power Station.

(C) This license shall be deemed to contain and is subject to.the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.D. below) and is subject-to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

Maximum Power Level Philadelphia Electric Company is authorized to operate that facility at reactor core-power levels of 3458 megawatts thdraal (100 percent rated power) in accordance with the conditions specified herein.

(2)

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.

, are hereby incorporated into this license. Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3)

Fire Protection (Section 9.5. SSER-2.-4)*

Philadelphia Electric 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 August 1983 through Supplement 9, dated August 1989, and I

Safety Evaluation dated November 20, 1995, subject to the following provision.

i The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those l

changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

  • The parenthetical notation following the title of license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.

LIMERICK - UNIT 2 Amendment No. 1,27,51,68

i (4)

Physical Security and Safeauards The licensee shall fully implement and maintain in effect all provisions of the physical security, guard training and qualification and safeguards contingency plans previously approved by the Comission and all amendments and revisions to such plans made pursuant to the authority of 10 CFR 50.90 and.10 CFR 50.54(p). The plant, which contain Safeguards Infonnation protected under 10 CFR 73.21, are entitled: " Limerick Generating Station, Units 1 & 2, Physical Security Plan," with revisions submitted through October 31,1988; " Limerick Generating Station,-

Units 1 & 2, Plant Security Personnel Training and Qualification Plan," with revisions submitted through October 1, 1985; and

" Limerick Generating Station Units 1 & 2, Safeguards Contingency Plan," with revisions submitted through November 15, 1986.

D. The facility requires exemptions from certain requirements of 10 CFR Part 50'and 10 CFR Part 70. These include (a) exemption from the requirement of paragraph III.D.2.(b)(ii) of Appendix J, the testing of containment air locks at times when the containment integrity is not required (Section 6.2.6.1.of the SER and SSER-3)

(b) exemption from the requirements of paragraphs II.H.4 and III.C.1 of Appendix J, the leak rate testing of the Main Steam Isolation Valves (MSIVs) at the peak calculated containment pressure, Pa, and exemption from the requirements of paragraph III.C.3 of Appendix J that the measured MSIV leak rates be included in the summation for 1

the local leak rate test (Section 6.2.6.1 of SSER-3), (c) exemption from the requirement of paragraphs II.H.1 and III.C.2 of Appendix J, i

l P

LIMERICK - UNIT 2 Amendment No.68

y LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS l

SECTION p.gg INSTRUMENTATION (Continued)

Table 4.3.7.1-1 Radiation Monitoring Instrumentation Surveillance Requirements.......................

3/4 3-66 The information from pages 3/4 3-68 i

through 3/4 3-72 has been intentionally omitted. Refer to note on page 3/4 3-68.............

3/4 3-68 The information from pages 3/4 3-73 through 3/4 3-75 has been intentionally omitted. Refer to note on page 3/4 3-73.............

3/4 3-73 Remote Shutdown System Instrumentation and Controls.....

3/4 3-76 Table 3.3.7.4-1 Remote Shutdown System Instrumentation and Controls.......

3/4 3-77 Table 4.3.7.4-1 Remote Shutdown System Instrumentation Surveillance Requirements.......................

3/4 3-83 Accident Monitoring Instrumentation.....................

3/4 3-84

,I Table 3.3.7.5-1 Accident Monitoring Instrumen-tation.............................

3/4 3-85 Table 4.3.7.5-1 Accident Monitoring Instrumenta-tion Surveillance Requirements.....

3/4 3-87 Source Range Monitors...................................

3/4 3-88 Traversing In-Core Probe System.........................

3/4 3-89 j

Chlorine Detection System...............................

3/4 3-90 Toxic Gas Detection System..............................

3/4 3-91 DELETED; Refer to note on page..........................

3/4 3-92 l i

i l

LIMERICK - UNIT 2 ix Amendment No. H,36,68 i

M LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION MGE PLANT SYSTEMS (Continued) 3/4.7.2 CONTROL ROOM EMERGENCY FRESH AIR SUPPLY SYSTEM - COMON SYSTEM.....................................................

3/4 7-6 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM......................

3/4 7-9 3/4.7.4 SNUBBERS...................................................

3/4 7-11 Figure 4.7.4-1 Sample Plan 2) For Snubber Functional Test.........................

3/4 7-16 3/4.7.5 SEALED SOURCE CONTAMINATION.............................*

3.4 7-17 3/4.7.6 DELETED; Refer to note on page..........................

3/4 7-19 l

3/4.7.7 DELETED; Refer to note on page...........................

3/4 7-19 3/4.7.8 MAIN TURBINE BYPASS SYSTEM..............................

3/4 7-33 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES A.C.

Sources - Operating................................

3/4 8-1 Table 4.8.1.1.2-1 Diesel Generator Test Schedule........................

3/4 8-8 l

A.C. Sources - Shutdown..................................

3/4 8-9 3/4.8.2 D.C. SOURCES D.C. Sources - Operating.................................

3/4 8-10 LIMERICK - UNIT 2 xiv Amendment No. 46,68

~

.lfiDfl BASES SECTION Egg INSTRUMENTATION (Continued)

(Deleted).................................................

B 3/4 3-5 (Deleted).................................................

B 3/4 3-5 Remote Shutdown System Instrumentation and Controls.......

B 3/4 3-5 Accident Monitoring Instrumentation.......................

B 3/4 3-5 Source Range Monitors......................................

B 3/4 3-5 Traversing In-Core Probe System...........................

B 3/4 3-6 Chlorine and Toxic Gas Detection Systems..................

B 3/4 3-6 (Deleted).................................................

B 3/4 3-6 Loose-Part Detection System...............................

B 3/4 3-7 (0eleted).................................................

B 3/4 3-7 Offgas. Monitoring Instrumentation.........................

B 3/4 3-7

.l 3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM.......................

B 3/4 3-7 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION...........................................

B 3/4 3-7 Bases Figure B 3/4.3-1 Reactor Vessel Water Leve1........................

B 3/4 3-8 3/4.4 REACTOR COOLANT SYSIEH 3/4.4.1 RECIRCULATION SYSTEM....................................

B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES....................................

B 3/4 4-2 i

3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems...............................

B 3/4 4-3 Operational Leakage......................................

B 3/4 4-3 3/4.4.4 CHEMISTRY...............................................

B 3/4 4-3a LIMERICK - UNIT 2 xix Anendment No. 41,12,17,32.36,68 4

IMEX BASES SECTION gig CONTAINMENT SYiTEMS (Continued) 3/4.6.3 PRIMARY CONTAINMENT ISOLATILW VALVES..............

B 3/4 6-4 3/4.6.4 VACUUM RELIEF.....................................

B 3/4 6-4 3/4.6.5 SECONDARY CONTAINMENT.............................

B3/46-5 3/4.6.6 PRIMARY CONTAllmENT ATM0 SPHERE CONTROL............

B 3/4 6-6 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS - COMON SYSTEMS............

B 3/4 7-1 3/4.7.2 CONTROL ROOM EMERGENCY FRESH AIR SUPPLY SYSTEM -

COMMON SYSTEM.....................................

B 3/4 7-1 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM.............

B 3/4 7-la 3/4.7.4 SNUBBERS..........................................

B 3/4 7-2 3/4.7.5 SEALED SOURCE CONTAMINATION.......................

B 3/4 7-3 3/4.7.6 (Deleted).........................................

B 3/4 7-4 3/4.7.7 (Deleted).........................................

B 3/4 7-4 3/4.7.8 MAIN TURBINE BYPASS SYSTEM........................

B 3/4 7-5 3/4.8 ELECTRICAL POWER SYSTEM 3/4.8.1,3/4.8.2,and 3/4.8.3 A.C. SOURCES, D.C. SOURCES, AND ONSITE POWER DISTRIBUTION SYSTEMS.................................

B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES...........

B 3/4 8-3

?/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH...............................

B 3/4 '9-1 3/4.9.2 INSTRUMENTATION...................................

B 3/4 9-1 3/4.9.3 CONTROL R00 P0SITION..............................

B 3/4 9-1 3/4.9.4 DECAY TIME........................................

B 3/4 9-1 3/4.9.5 C0fmVNICATIONS....................................

B3/49-1 LIMERICK - UNIT 2 xxi Amendment 16,68

..-...~ -.-.

INSTRUMENTATION Section 3/4.7.9 (Deleted)

W i

i -

[

i

]

i 1

i i

)

THE INFORMATION FRON THIS TECHNICAL SPECIFICATIONS SECTION i

HAS BEEN RELOCATED TO THE TECHNICAL REQUIREMENTS MANUAL (TRM) FIRE PROTECTION SECTION. TECHNICAL SPECIFICATIONS PAGES 3/4 3-92 THROUGH l

3/4 3-96 0F THIS SECTION HAVE BEEN INTENTIONALLY OMITTED.

LINERICK - UNIT 2 3/4 3-92 Amendment No. 25, 68

=

PLANT SYSTEMS Section 3/4.7.6 throuch 3/4.7.7 (Deleted) l THE INFORMATION FROM THESE TECHNICAL SPECIFICATIONS SECTIONS HAVE BEEN RELOCATED TO THE TECHNICAL REQUIREMENTS MANUAL (TRM) FIRE PROTECTION SECTION. 1ECHNICAL SPECIFICATIONS PAGES 3/4 7-19 THROUGH 3/4 7-32 HAVE BEEN INTENTIONALLY OMITTED.

LIMERICK - UNIT 2 3/4 7-19 Amendment No. 68

INSTRUMENTATION BASES 3/4.3.7.7 TRAVERSING IN-CORE PROBE SYSTEM The OPERA 8ILITY of the traversing in-core probe system with the specified minimum complement d e s peent ensures that the measurements obtained from use of this equipment accurately represent the spacial neutron flux distribution of the reactor core.

The TIP system operability is demonstrated by normalizing all probes (i.e.,

detectors) prior to performing an LPRM calibration function. Monitoring core thermal limits may involve utilizing individual detectors to monitor selected areas of the reactor core, thus all detectors may not be required to be OPERA 8LE. The OPERA 8ILITY of individual detectors to be used for monitoring is demonstrated by comparing the detector (s) output in the resultant heat balance calculation (P-1) with data obtained during a previous heat balance calculation (P-1).

3/4.3.7.8 CHLORINE AND T0XIC GAS DETECTION SYSTEMS The OPERABILITY of the chlorine and toxic gas detection systems ensures that an accidental chlorine and/or toxic gas release will be detected promptly and the necessary protective actions will be automatically initiated for chlo-rine and manually initiated for toxic gas to provide protection for control room personnel. Upon detection of a high concentration of chlorine, the control room emergency ventilation system will automatically be placed in the chlorine isolation mode of operation to provide the required protection. Upon detection of a high concentration of toxic gas, the control room one ency ventilation system will manually be placed in the chlorine isolation e of operation to provide the required protection. The detection systems required by this speci-fication are consistent with the recommendations of Regulatory Guide 1.95, " Pro-tection of Nuclear Power Plant Control Room Operators against an Accidental Chlorine Release," February 1975.

There are three toxic gas detection subsystems. The high toxic chemical concentration alarm in the Main Control Room annunciates when two of the three subsystems detect a high toxic gas concentration. An Operate /Inop keylock switch is provided for each subsystem which allows an individual subsystem to be placed in the tripped condition.

Placing the keylock switch in the INOP position initiates one of the two inputs required to initiate the alarm in the Main Control Room.

Specified surveillance intervals and maintenance outage times have been determined in accordance with GENE-770-06-1, " Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications," as approved by the NRC and documented in the SER (letter to R.D.

Binz, IV, from C.E. Rossi dated July 21,1992).

3/4.3.7.9 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE TRM.

l LIMERICK - UNIT 2 B 3/4 3-6 Amendment No. 44,25,33,45, 68

i INSTRUMENTATION BASES 3/4.3.7.10 L001E PART DETECTION SYSTEN The OPERASILITY of the loose-part detection system ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components. The allowable out-of-service times and surveillance requirements are consistent with the recom-mandations of Regulatory Guide 1.133, " Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors," May 1981.

3/4.3.7.11 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE 00CM.

3/4.3.7.12 0FFGAS MONITORING INSTRUMENTATION This instrumentation includes provisions for monitoring the concentrations of potentially explosive gas mixtures and noble gases in the off-gas system.

3/4.3.8 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE UFSAR.

3/4 3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION The feedwater/ main turbine trip system actuation instrumentation is provided to initiate action of the feedwater system / main turbine trip system in the event of failure of feedwater controller under maximum demand LIMERICK - UNIT 2 B 3/4 3-7 Amendment No. ff,25,33,64,68

PLANT SYSTEMS BASES 3/4 7.6 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE TRM.

3/4.7.7 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE TRM.

LIMERICK - UNIT 2 B 3/4 7-4 Amendment No.68

ADMINISTRATIVE CONTROLS 6.2.2 UNIT STAFF a.

Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2.2-1; b.

At least one licensed Operator shall be in the control room when fuel is in the reactor.

In addition, while the unit is in OPERATIONAL

. CONDITION 1, 2, or 3, at least one licensed Senior Operator shall be in the control room:

c.

A Health Physics Technician

  • shall be on site when. fuel is in the i

reactor; d.

ALL CORE ALTERATIONS shall be observed and directly. supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation; e.

(Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE TRM.

f.

Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions (e.g., licensed Senior Operators, licensed Operators, health physi-cists, auxiliary operators, and key maintenance personnel).

Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the unit is operating.

However, in the event that unforeseen problems require substantia amounts of overtime to be used, or during extended periods of shut-down for refueling, major maintenance, or major unit modifications, on a temporary basis the following guidelines shall be followed:

1.

An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.

2.

An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all excluding shift turnover time.

  • The Health Physics Technician position 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, provided immediate action is taken to fill the required position.

LIMERICK - UNIT 2 6-2 Amendment No. 2,W,68

ADMINISTRATIVE CONTROLS j

RESPONSIBILITIES i

6.5.1.6 The PROC 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 1

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; I

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 1

that affect nuclear safety; i

e.

DELETED.

f.

Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evaluation and i

recommendations to prevent recurrence, to the Vice President, Limerick Generating Station, Plant Manager, and to the Nuclear Review Board; g.

Review of all REPORTA8LE EVENTS; h.

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

Perfomance of special reviews, investigations, or analyses and reports thereon as requested by the Vice President, Limerick Generating Station, plant Manager or the Chairman of the Nuclear Review Board; J.

Review of the Security Plan and implementing procedures and submittal of recommended changes to the Nuclear Review Board; and

)

k.

Review of the Emergency Plan and implementing procedures and submittal of the recomunended 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, recomunendations and disposition of the corrective action to prevent recurrence to the Vice President, Limerick Generating Station, Plant Manager, and to the Nuclear Review Board, m.

Review of changes to the PROCESS CONTROL PROGRAM, 0FFSITE DOSE CALCULATION MANUAL, and radwaste treatment systems.

n.

Review of the Fire Protection Program and implementing procedures and the submittal of recommended changes to the Nuclear Review Board.

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.

LIMERICK - UNIT 2 6-8 Amendment No. 40,68

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