ML073461114

License Amendment Request - Proposed Administrative Changes to Technical Specification

ML073461114
Person / Time
Site:	Limerick
Issue date:	12/12/2007
From:	Cowan P Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML073461114 (44)

Text

Exclon Nuclear \n~~u~+!.exeloniorp.corn zoo Exelon LVay Nuclear Kennett Square, PA 19348 10 CFR 50.90 December 12,2007 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Limerick Generating Station, Units 1 and 2 Facility Operating License Nos. NPF-39 and NPF-85 NRC n o c k e t - 5 0 - 3 5 2 50-w

SUBJECT:

License Amendment Request Proposed Administrative Changes to Technical Specifications Pursuant to 10 CFR 50.90, "Application for amendment of license or construction permit,"

Exelon Generation Company, LLC (Exelon), proposes changes to the Technical Specifications (TS), Appendix A of Operating License Nos. NPF-39 and NPF-85 for Limerick Generating Station (LGS), Units 1 and 2, respectively.

The proposed administrative changes provide an editorial cleanup of the TS. The proposed changes involve: ( I ) correcting the index, (2) removing cycle specific requirements or notes that have since expired and are no longer applicable, (3) deleting references to previously deleted requirements, (4) changing references to the location of previously relocated information, and (5) editorial corrections. Evaluation of the proposed changes is provided in this attachment.

Markups of the proposed TS changes are provided in Attachment 2.

Exelon has concluded that the proposed changes present no significant hazards consideration under the standards set forth in 10CFR 50.92.

This amendment request contains no regulatory commitments.

Exelon requests approval of the proposed amendment by December 12,2008. Upon NRC approval, the amendment shall be implemented within 60 days of issuance.

These proposed changes have been reviewed by the Plant Operations Review Committee and approved in accordance with Nuclear Safety Review Board procedures.

License Amendment Request Administrative Changes Docket Nos. 50-352 and 50-353 December 12,2007 Page 2 We are notifying the State of Pennsylvania of this application for changes to the Technical Specifications by transmitting a copy of this letter and its attachments to the designated State Official.

If you have any questions or require additional information, please contact Glenn Stewart at 610-765-5529.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 12th day of December, 2007.

Respectfully, Pamela 6.&wan Director, Licensing & Regulatory Affairs Exelon Generation Company, LLC Attachments: 1. Evaluation of Proposed Changes

2. Markup of Proposed Technical Specifications Pages cc: Regional Administrator - NRC Region I W/ attachments NRC Senior Resident Inspector - Limerick Generating Station It NRC Project Manager, NRR - Limerick Generating Station It Director, Bureau of Radiation Protection - Pennsylvania Department If of Environmental Protection

ATTACHMENT 1 License Amendment Request Limerick Generating Station, Units 1 and 2 Docket Nos. 50-352 and 50-353 EVALUATION OF PROPOSED CHANGES

Subject:

Proposed Administrative Changes to Technical Specifications

2.0 PROPOSED CHANGE

S

7.0 REFERENCES

License Amendment Request Attachment 1 Administrative Changes Page 1 of 9 Docket Nos. 50-352 and 50-353 Evaluation of Proposed Changes

1.0 DESCRIPTION

Pursuant to 10 CFR 50.90, Application for amendment of license or construction permit, Exelon Generation Company, LLC (Exelon), proposes changes to the Technical Specifications (TS), Appendix A of Operating License Nos. NPF-39 and NPF-85 for Limerick Generating Station (LGS), Units 1 and 2, respectively.

The proposed administrative changes provide an editorial cleanup of the TS. The proposed changes involve: (1) correcting the index, (2) removing cycle-specific requirements or notes that have since expired and are no longer applicable, (3) deleting references to previously deleted requirements, (4) changing references to the location of previously relocated information, and (5) editorial corrections. Evaluation of the proposed changes is provided in this attachment. Markups of the proposed TS changes are provided in Attachment 2.

2.0 PROPOSED CHANGE

S The changes requested by this amendment application are described below.

1. Index Corrections a) LGS, Units 1 and 2 - Revise Index page ii to reflect the previously approved addition of TS Definition 1.35, "RECENTLY IRRADIATED FUEL" to TS page 1-6 and TS Definition 1.37a, "RESTRICTED AREA" to TS page 1-7, and the appropriate renumbering of the remaining TS Definitions.

b) LGS, Units 1 and 2 - Change the word "Semiannual" to "Annual" in the title of the Radioactive Effluent Release Report on TS Index page xxvii to reflect the appropriate title for the report as specified under Section 6.9.1, "Routine Reports,"

on TS page 6-17.

2. Cycle-Specific Requirements or Notes that are No Longer Applicable a) LGS, Unit 1 - Delete Limiting Condition for Operation (LCO) 3.1.3.6, Action c. and associated Surveillance Requirement (SR) 4.1.3.6.d relative to repositioning uncoupled control rod 50-27. Also, delete the words "except as in 3.1.3.6.c or" from LCO 3.1.3.6, Action a.2. These requirements were limited to LGS, Unit 1, Cycle 7 only. LGS, Unit 1 is currently operating in Cycle 12. Therefore, these requirements are no longer applicable.

b) LGS, Unit 2 - Delete the double asterisk and associated footnote from the 145oF drywell average air temperature limit specified in TS LCO 3.6.1.7 and associated TS Action. This footnote was limited to LGS, Unit 2, Cycle 9 only. LGS, Unit 2 is currently operating in Cycle 10. Therefore, this footnote is no longer applicable.

License Amendment Request Attachment 1 Administrative Changes Page 2 of 9 Docket Nos. 50-352 and 50-353 Evaluation of Proposed Changes

3. References to Previously Deleted Requirements a) LGS, Units 1 and 2 - Delete the reference to TS SR 4.8.1.1.3 from TS SR 4.8.1.2 on TS page 3/4 8-9 since TS SR 4.8.1.1.3 was previously deleted and is no longer in TS.

4. References to the Location of Previously Relocated Information a) LGS, Units 1 and 2 - Replace the word "UFSAR" with the word "TRM" in the relocation information provided of TS pages 3/4 3-68, 3/4 3-110, 3/4 6-49, 3/4 6-51, 3/4 6-51a, and 3/4 8-21.

5. Editorial Changes a) LGS, Unit 2 - Capitalize the first letter "r" in the word "radioactive" in the title of the Radioactive Effluent Controls Program referenced under Item No. (1) in TS Definition 1.24 (OFFSITE DOSE CALCULATION MANUAL) on TS page 1-4.

b) LGS, Unit 2 - Replace misspelled word "RELOCATD" with the word "RELOCATED" on TS page 3/4 3-110.

c) LGS, Units 1 and 2 - Replace capitalized word "INOPERABLE" with lower case word "inoperable" in TS LCO 3.4.3.1, Actions B, C, D, and E on TS page 3/4 4-8.

d) LGS, Unit 2 - Replace the word "or" with the word "of" in TS SR 4.4.3.1.b on TS page 3/4 4-8a.

e) LGS, Units 1 and 2 - Replace the word "patch" with the word "path" in TS LCO 3.5.1.a.2 on TS page 3/4 5-1.

f) LGS, Units 1 and 2 - Delete the "s" at the end of the word "valves" and replace the word "the" with the word "each" in TS LCO 3.6.3 on TS page 3/4 6-17.

g) LGS, Unit 1 - Change the paragraph indent for TS SR 4.7.1.2.b.2 to line up with the paragraph indent for TS SR 4.7.1.2.b.1 on TS page 3/4 7-4.

h) LGS, Unit 2 - Delete the duplicate word "both" from the first sentence in TS LCO 3.7.2, Action b.2 on TS page 3/4 7-6.

3.0 BACKGROUND

As a result of various changes to TS that have been requested and approved over time, a number of minor inconsistencies or editorial errors that have no safety impact have been introduced into the LGS Unit 1 and Unit 2 TS. The purpose of this amendment request is to correct those inconsistencies or errors.

License Amendment Request Attachment 1 Administrative Changes Page 3 of 9 Docket Nos. 50-352 and 50-353 Evaluation of Proposed Changes

4.0 TECHNICAL ANALYSIS

The Technical justification for each of the changes proposed in Section 2.0 of this request is provided below.

1. Index Corrections By letter dated August 23, 2006 (Reference 1), the NRC issued Amendment No. 185 to Facility Operating License No. NPF-39 and Amendment No. 146 to Facility Operating License No. NPF-85 for LGS, Units 1 and 2, respectively. These amendments revised LGS TS to support application of an alternate source term methodology. These amendments approved the addition of Definition No. 1.35 (RECENTLY IRRADIATED FUEL) to TS Section 1.0, "DEFINITIONS," on TS page 1-

6. As a result of this addition, pre-existing Definition Nos. 1.35 (REFUELING FLOOR SECONDARY CONTAINMENT INTEGRITY), 1.36 (REPORTABLE EVENT), 1.37 (ROD DENSITY), 1.38 (SHUTDOWN MARGIN), and 1.39 (SITE BOUNDARY) were renumbered to 1.36 through 1.40, respectively.

By letter dated June 29, 2007 (Reference 2), the NRC issued Amendment No. 187 to Facility Operating License No. NPF-39 and Amendment No. 148 to Facility Operating License No. NPF-85 for LGS, Units 1 and 2, respectively. These amendments revised LGS TS to incorporate revised requirements from Title 10 of the Code of Federal Regulations (CFR), Part 20. These amendments added Definition No. 1.37a (RESTRICTED AREA), to TS Section 1.0 on TS page 1-7.

By letter dated August 10, 1994 (Reference 3), the NRC issued Amendment No. 73 to Facility Operating License No. NPF-39 and Amendment No. 35 to Facility Operating License No. NPF-85 for LGS, Units 1 and 2, respectively. These amendments revised various LGS TS sections to change the frequency for submitting the Semiannual Radioactive Effluent Release Report to the NRC from semiannually to annually. These changes involved changing the title of TS Section 6.9.1.8 on TS page 6-17 from "Semiannual Radioactive Effluent Release Report" to "Annual Radioactive Effluent Release Report."

All of these amendments were approved as requested by Exelon; however, the Exelon requests did not include a revised TS Index to reflect the associated changes to TS Sections 1.0 or 6.9.1. The proposed changes described in this amendment request revise the TS Index to appropriately reflect the changes to these sections of TS that were previously approved by the amendments referenced above. The proposed changes are administrative in nature and do not involve any physical changes to structures, systems, or components (SSCs) in the plant, or the way SSCs are operated or controlled.

License Amendment Request Attachment 1 Administrative Changes Page 4 of 9 Docket Nos. 50-352 and 50-353 Evaluation of Proposed Changes

2. Cycle-Specific Requirements or Notes that are No Longer Applicable By letter dated January 16, 1998 (Reference 4), the NRC issued Amendment No. 124 to Facility Operating License No. NPF-39 for LGS, Unit 1. This amendment revised TS LCO 3.1.3.6 and associated TS SR 4.1.3.6 to allow operation of the unit with control rod 50-27 uncoupled from its drive for the remainder of operating Cycle 7.

This amendment specified the conditions under which control rod 50-27 could be manipulated and modified the surveillance requirements to verify control rod position using neutron instrumentation. LGS, Unit 1 completed operating Cycle 7 in April, 1998, when the unit was shutdown for refueling outage 1R07, during which time the control rod drive was replaced and control rod 50-27 was re-coupled. LGS, Unit 1 is currently operating in Cycle 12. As a result, these requirements are no longer applicable. Therefore, the proposed change deletes LCO 3.1.3.6.c and SR 4.1.3.6.d from the LGS, Unit 1 TS, and deletes the words "except as in 3.1.3.6.c or" from LGS, Unit 1 LCO 3.1.3.6, Action a.2.

By letter dated July 7, 2006 (Reference 5), the NRC issued Amendment No. 145 to Facility Operating License No. NPF-85 for LGS, Unit 2. This amendment approved a one-time change to TS LCO 3.6.1.7 by adding a footnote (**) to the TS limit for drywell average air temperature of 145 degrees Fahrenheit (oF) to allow continued operation of LGS, Unit 2, with drywell average air temperature no greater than 148oF for the remainder of operating Cycle 9, or until the next shutdown of sufficient duration to allow for unit cooler fan repairs, whichever came first. LGS, Unit 2 completed operating Cycle 9 in March, 2007, when the unit was shutdown for refueling outage 2R09, during which the unit cooler fans were repaired. LGS, Unit 2 is currently in operating Cycle 10. As a result, this footnote is no longer applicable.

Therefore, the proposed change deletes this footnote from LGS, Unit 2, LCO 3.6.1.7.

The proposed changes are administrative in nature and do not involve any physical changes to SSCs in the plant, or the way SSCs are operated or controlled.

3. References to Previously Deleted Requirements By letter dated November 6, 2007 (Reference 6), the NRC issued Amendment No.

189 to Facility Operating License No. NPF-39 and Amendment No. 150 to Facility Operating License No. NPF-85 for LGS, Units 1 and 2, respectively. These amendments modified emergency diesel generator (EDG) testing requirements to improve EDG reliability by reducing potential equipment degradation due to excessive testing. These amendments approved the deletion of SR 4.8.1.1.3 which required a special report to be submitted to the NRC within 30 days of all EDG failures.

TS Section 3.8.1 specifies the LCO and SR requirements for both A.C. Sources -

Operating (LCO 3.8.1.1) and A.C. Sources - Shutdown (LCO 3.8.1.2). SR 4.8.1.1.3 was previously specified under A.C. Sources - Operating. However, the operability of A.C. Sources - Shutdown is demonstrated by performing SR 4.8.1.2, which references the surveillance requirements under A.C. Sources - Operating, including

License Amendment Request Attachment 1 Administrative Changes Page 5 of 9 Docket Nos. 50-352 and 50-353 Evaluation of Proposed Changes SR 4.8.1.1.3. SR 4.8.1.1.3 was an administrative requirement for reporting to the NRC and did not, in and of itself, help to demonstrate the operability of the A.C.

Sources. Deleting this reporting requirement did not impact the safe operation of the plant and was approved by the NRC in the amendment referenced above. Therefore, the proposed change deletes the reference to previously deleted SR 4.8.1.1.3 from SR 4.8.1.2, and makes an associated editorial change to SR 4.8.1.2 regarding the reference to the remaining SRs 4.8.1.1.1 and 4.8.1.1.2.

The proposed change is administrative in nature and does not involve any physical changes to SSCs in the plant, or the way SSCs are operated or controlled.

4. References to the Location of Previously Relocated Information The information provided in TS Sections 3/4.3.7.2, 3/4.3.8, 3.6.5.2.1, 3.6.5.2.2 and 3/4.8.4.1 was previously relocated to licensee documents that are controlled under the requirements of 10 CFR 50.59 based on NRC approved amendments.

Specifically, by letter dated August 29, 1994 (Reference 7), the NRC issued Amendment No. 75 to Facility Operating License No. NPF-39 and Amendment No. 36 to Facility Operating License No. NPF-85 for LGS, Units 1 and 2, respectively. These amendments relocated the seismic monitoring instrumentation requirements from TS Section 3/4.3.7.2 to the Updated Final Safety Analysis Report (UFSAR).

By letter dated August 24, 1995 (Reference 8), the NRC issued Amendment No. 100 to Facility Operating License No. NPF-39 and Amendment No. 64 to Facility Operating License No. NPF-85 for LGS, Units 1 and 2, respectively. These amendments relocated the turbine overspeed protection system requirements from TS Section 3/4.3.8 to the UFSAR.

By letter dated November 20, 1995 (Reference 9), the NRC issued Amendment No.

105 to Facility Operating License No. NPF-39 and Amendment No. 69 to Facility Operating License No. NPF-85 for LGS, Units 1 and 2, respectively. These amendments relocated the Reactor Enclosure and Refueling Area Secondary Containment Automatic Isolation Valves from TS Sections 3.6.5.2.1 and 3.6.5.2.2, respectively, to the UFSAR.

By letter dated June 22, 1995 (Reference 10), the NRC issued Amendment No. 93 to Facility Operating License No. NPF-39 and Amendment No. 57 to Facility Operating License No. NPF-85 for LGS, Units 1 and 2, respectively. These amendments relocated the primary containment conductor protection device requirements from TS Section 3/4.4.8.1 to the UFSAR.

TS pages 3/4 3-68, 3/4 3-110, 3/4 6-49, 3/4 6-51, 3/4 6-51a, and 3/4 8-21 each indicate that the information from their respective TS sections was relocated to the UFSAR. Subsequent to implementation of the above license amendments, LGS implemented a Technical Requirements Manual (TRM), which is incorporated into the

License Amendment Request Attachment 1 Administrative Changes Page 6 of 9 Docket Nos. 50-352 and 50-353 Evaluation of Proposed Changes LGS UFSAR by reference and is controlled under the requirements of 10 CFR 50.59.

The TRM contains the technical requirements that are relocated from TS as approved by the NRC via license amendments. Once the TRM was established, the technical requirements that had previously been removed from TS and relocated to the UFSAR via the license amendments referenced above were transferred from the UFSAR to the TRM under the requirements of 10 CFR 50.59. Although the reference to the UFSAR on these TS pages is technically correct, since the TRM is incorporated into the UFSAR by reference, the proposed change replaces the word "UFSAR" with the word "TRM" to more explicitly state the current location of the technical requirements relocated from these TS pages. The proposed change is administrative in nature and does not involve any physical changes to SSCs in the plant, or the way SSCs are operated or controlled.

5. Editorial Changes The changes described under Item 5 of Section 2.0 strictly involve editorial changes to correct typographical errors, grammar, and paragraph indentation, and delete duplicate wording. These proposed changes are non-substantive changes that have no impact on safe operation of the plant in that they do not involve any physical changes to SSCs in the plant, or the way SSCs are operated or controlled.

5.0 REGULATORY ANALYSIS

5.1 No Significant Hazards Consideration Exelon has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, Issuance of amendment, as discussed below:

1. Do the proposed changes involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No. The proposed changes are administrative in nature and do not impact the physical configuration or function of plant structures, systems, or components (SSCs) or the manner in which SSCs are operated, maintained, modified, tested, or inspected. The proposed changes do not impact the initiators or assumptions of analyzed events, nor do they impact mitigation of accidents or transient events. Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

License Amendment Request Attachment 1 Administrative Changes Page 7 of 9 Docket Nos. 50-352 and 50-353 Evaluation of Proposed Changes

2. Do the proposed changes create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No. The proposed changes are administrative in nature and do not alter plant configuration, require that new plant equipment be installed, alter assumptions made about accidents previously evaluated, or impact the function of plant SSCs or the manner in which SSCs are operated, maintained, modified, tested, or inspected. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Do the proposed changes involve a significant reduction in a margin of safety?

Response: No. The proposed changes are administrative in nature and do not involve any physical changes to plant SSCs or the manner in which SSCs are operated, maintained, modified, tested, or inspected. The proposed changes do not involve a change to any safety limits, limiting safety system settings, limiting conditions of operation, or design parameters for any SSC. The proposed changes do not impact any safety analysis assumptions and do not involve a change in initial conditions, system response times, or other parameters affecting an accident analysis. Therefore, the proposed changes do not involve a significant reduction in a margin of safety.

Based on the above, Exelon concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of no significant hazards consideration is justified.

5.2 Applicable Regulatory Requirements/Criteria In Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, the Nuclear Regulatory Commission (NRC) established its regulatory requirements related to the content of TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls. The regulation does not specify the particular requirements to be included in a plants TSs.

The proposed changes are administrative in nature and do not involve any physical changes to plant SSCs or the manner in which SSCs are operated, maintained, modified, tested, or inspected. The proposed changes do not involve a change to any safety limits, limiting safety system settings, limiting control settings, limiting conditions of operation, surveillance requirements, design features, or administrative controls required by 10 CFR 50.36.

License Amendment Request Attachment 1 Administrative Changes Page 8 of 9 Docket Nos. 50-352 and 50-353 Evaluation of Proposed Changes In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

6.0 ENVIRONMENTAL CONSIDERATION

A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

7.0 REFERENCES

1. Letter dated August 23, 2006, from R. Guzman, USNRC to C. Crane, Exelon Nuclear, "Limerick Generating Station, Units 1 and 2 - Issuance of Amendments RE:

Application of Alternate Source Term Methodology (TAC Nos. MC2295 and MC2296)."

2. Letter dated June 29, 2007, from P. Bamford, USNRC to C. Crane, AmerGen Energy Company, "Limerick Generating Station, Units 1 and 2 - Issuance of Amendment RE:

Incorporation of Revised 10 CFR Part 20 Requirements into the Technical Specifications (TAC Nos. MD4946 and MD4947)."

3. Letter dated August 10, 1994, from F. Rinaldi, USNRC to G. Hunger, Philadelphia Electric Company, "Frequency for Submitting Semiannual Radioactive Effluent Release Report, Limerick Generating Station, Units 1 and 2 (TAC Nos. M89175 and M89176)."

4. Letter dated January 16, 1998, from B. Buckley, USNRC to G. Hunger, PECO Energy Company, "Revision to Technical Specifications Regarding Control Rod 50-27, Limerick Generating Station, Unit 1 (TAC Nos. M99854 and M99855)."

5. Letter dated July 7, 2006, from R. Guzman, USNRC to C. Crane, Exelon Nuclear, "

Limerick Generating Station, Unit 2 - Issuance of Amendment RE: One-Time Change to the Drywell Average Air Temperature Limit (TAC No. MD2315)."

License Amendment Request Attachment 1 Administrative Changes Page 9 of 9 Docket Nos. 50-352 and 50-353 Evaluation of Proposed Changes

6. Letter dated November 6, 2007, from P. Bamford, USNRC to C. Crane, Exelon Generation Company, LLC, "Limerick Generating Station, Units 1 and 2 - Issuance of Amendment RE: Changes to Technical Specification Emergency Diesel Generator Testing Requirements (TAC Nos. MD3710 and MD3711)."

7. Letter dated August 29, 1994, from F. Rinaldi, USNRC to G. Hunger, Philadelphia Electric Company, "Relocation of Seismic Monitoring Equipment, Limerick Generating Station, Units 1 and 2 (TAC Nos. M88608 and M88655)."

8. Letter dated August 24, 1995, from F. Rinaldi, USNRC to G. Hunger, PECO Energy Company, "Relocation of Turbine Overspeed Protection System Requirements, Limerick Generating Station, Units 1 and 2 (TAC Nos. M90375 and M90376)."

9. Letter dated November 20, 1995, from F. Rinaldi, USNRC to G. Hunger, PECO Energy Company, "Limerick Generating Station, Units 1 and 2 (TAC Nos. M93690 and M93691)."

10. Letter dated June 22, 1995, from F. Rinaldi, USNRC to G. Hunger, PECO Energy Company, "Relocation of Primary Containment Conductor Protection Device Requirements, Limerick Generating Station, Units 1 and 2 (TAC Nos. M90375, M90376, M90512, and M90513)."

ATTACHMENT 2 License Amendment Request Limerick Generating Station, Units 1 and 2 Docket Nos. 50-352 and 50-353 Proposed Administrative Changes to Technical Specifications Markup of Proposed Technical Specifications Pages Unit 1 TS Pages ii xxvii 3/4 1-11 3/4 1-12 3/4 3-68 3/4 3-110 3/4 4-8 3/4 5-1 3/4 6-17 3/4 6-49 3/4 6-51 3/4 6-51a 3/4 7-4 3/4 8-9 3/4 8-21 Unit 2 TS Pages ii xxvii 1-4 3/4 3-68 3/4 3-110 3/4 4-8 3/4 4-8a 3/4 5-1 3/4 6-10 3/4 6-17 3/4 6-49 3/4 6-51 3/4 6-51a 3/4 7-6 3/4 8-9 3/4 8-21

JNDEX SECTION DEFINITIONS ( C o n t i n u e d ) -

PAGE LOW (PBWER) TRIP SETPOINT (LTSP). ... .................... 1-4 i

1.20a 1.21 (DELETED) ................................................... 1-4 1.22b MAPFAC( P) - (POWER DEPENDENT MAPLHGR MULTIPLIER). .......... 1-4 1.24 OFFSITE DOSE CALCULATION MANUAL.. .. .................... ... 1-4 1.25 OPERABLE - OPERABILITY.. .......... ............... ......... 1-4 1.26 OPERATIONAL CONDITION - CONDITION. ............... .. .. .... . . 1-5 1.27 PHYSICS TESTS ............................................... 1-5 1.28 PRESSURE BOUNDARY LEAKAGE.. ................................ 1-5 1.29 PRIMARY CONTAINMENT INTEGRITY. ...... .................... ... 1-5 1.30 PROCESS CONTROL PROGRAM. 1-5 1.31 PURGE - PURGING. ........................................... 1-6 1 1.32 RATED THERMAL POWER.. ...................................... 1-6 1.33 REACTOR ENCLOSURE SECONDARY CONTAINMENT INTEGRITY.. . ... ... 1-6 ME ....................

INTEGRITY ............

@ - " c C C ) c / C ~

S

.........................****....*..+$+;&7

& & # & & 4 & @ & 0 / @ # ~ I Y C ~

0 c w 3 > SHUTDOWN MARGI N............................................ 1-7 cxa SITE BOUNDARY.. ................................... . ..... ..

1.41 SOURCE CHECK ............................................... 1-7 1

LIMERICK - UNIT 1 ii Amendment No. $3, $8, 52, FEB 1 o 1994 66

Deleted I Deleted .................................................... 6-9 I Deleted .................................................... 6-9 I De'leted .................................................... 6-10 I Deleted .................................................... 6-10 I Deleted .................................................... 6-10 I Deleted .................................................... 6-10 I Deleted ....................................................6-10 I Deleted .................................................... 6-12 I 6.5.3 Deleted ........................................~...........6-12 I 5.6 RFPORTABLE EVENT AC TION ............................................6-12a 6.7 SAFFTY I I M I T VIOLATIOt( .............................................6-12a 6.8 PROCEDURFS AND P R O ~ R A M S............................................6-13 6.9 RFpORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS ............................................ 6-15 S t a r t u p Report .............................................6-15 Annual Reports ............................................. 6-15 Monthly O p e r a t i n g Reports .................................. 6-16 Annual R a d i o l o g i c a l Environmental Operating Report ......... 6-16 e n n u a l R a d i o a c t i v e E f f l u e n t Release Report .............6-17 CORE OPERATING LIMITS' REPORTS .............................. 6-18a 6.9.2 SPECIAL REPORTS ............................................ 6-18a 5-10 DELETED . .. . . . . . . . . . . 6-19 6.11 RADIATION PROTFCT I O N P R O M ......................................6-20 6.13 HIGH RADIATION ARF$ ............................................... 6-20 LIMERICK - UNIT 1 xxvi i Amendment No. 32, 42, 96, 176

REACTIVITY CONTROL SYSTEMS CONTROL ROD D R I V E COUPLING LIMITING CO NDITION FOR OPER AT ION 3.1.3.6 A l l c o n t r o l rods s h a l l be c o u p l e d t o t h e i r d r i v e mechanisms.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 5 " .

ACTION:

a. I n OPERATIONAL CONDITIONS 1 and 2 w i t h one c o n t r o l r o d n o t c o u p l e d t o i t s a s s o c i a t e d d r i v e mechanism, w i t h i n 2 h o u r s :

1. I f p e r m i t t e d by t h e RWM, i n s e r t t h e c o n t r o l r o d d r i v e mechanism t o accompl ish r e c o u p l in g and v e r i f y r e c o u p l i n g b y w i t h d r a w i n g t h e c o n t r o l r o d , and:

a) Observing any i n d i c a t e d response o f t h e n u c l e a r i n s t r u m e n t a -

t i o n , and b) D e m o n s t r a t i n g t h a t t h e c o n t r o l r o d w i l l n o t go t o t h e o v e r -

travel position.

O t h e r w i s e , be i n a t l e a s t HOT SHUTDOWN w i t h i n t h e n e x t 12 h o u r s .

2. I f recoupling i s n o t accomplis dac n o t p e r m i t t e d b y t h e RWM, t h e n I p e r m i t t e d by t h e RWM, d e c l a r e t h e c o n t r o l r o d and d i s a r m t h e a s s o c i a t e d d i r e c t i o n a l c o n t r o l valves** e i t h e r :

a) Electrically, or b) H y d r a u l i c a l l y b y c l o s i n g t h e d r i v e w a t e r and e x h a u s t w a t e r i s o l a t i o n valves.

O t h e r w i s e , be i n a t l e a s t HOT SHUTDOWN w i t h i n t h e n e x t 12 h o u r s .

b. In OPERATIONAL CONDITION 5" w i t h a w i t h d r a w n c o n t r o l r o d n o t c o u p l e d to i t s a s s o c i a t e d d r i v e mechanism, w i t h i n 2 h o u r s e i t h e r :

1. I n s e r t t h e c o n t r o l r o d t o a c c o m p l i s h r e c o u p l i n g and v e r i f y r e c o u p -

l i n g b y w i t h d r a w i n g t h e c o n t r o l r o d and d e m o n s t r a t i n g t h a t t h e c o n t r o l r o d w i l l n o t go t o t h e o v e r t r a v e l p o s i t i o n , o r

2. I f r e c o u p l i n g i s n o t a c c o m p l i s h e d , i n s e r t t h e c o n t r o l r o d and d i sarm t h e associ a t e d d i r e c t i o n a l c o n t r o l v a l v e s *

• e i t h e r :

a) Electrically, or b) H y d r a u l i c a l l y b y c l o s i n g t h e d r i v e w a t e r and e x h a u s t w a t e r e w i t h d r a w n when 1owi ng c o n d i t i o n s

1) The uncoupled c o n t r o l r o d may n o t b e w i t h d r a w n p a s t n o t c h p o s i t i o n 46, and

2) No o t h e r uncoupled c o n t r o l r o d i s w i t h d r a w n .

• A t l e a s t each w i t h d r a w n c o n t r o l r o d . N o t a p p l i c a b l e t o c o n t r o l r o d s removed p e r S p e c i f i c a t i o n 3.9.10.1 o r 3.9.10.2.

• • May b e rearmed i n t e r m i t t e n t l y , under a d m i n i s t r a t i v e c o n t r o l , t o p e r m i t t e s t i n g a s s o c i a t e d w i t h r e s t o r i n g t h e c o n t r o l r o d t o OPERABLE s t a t u s .

LIMERICK - UNIT 1 3/4 1-11 I Amendment No. -44, 224, 169

REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIWENTS 4.1.3.6 Each affected control rod shall be demonstrated t o be coupled t o i t s d r i v e mechanisnr by observlng any indicated response o f the nuclear instrumen-

~ tation while withdrawing the control rod t o the fully withdrawn posltton and then verjfying t h a t the control rod drfve does not go t o t h e overtravel posi t i on z

a. Prior t o reactor criticality after completing CORE ALTERATIONS t h a t could have affected the control rod drive coupling integrity,

b. Anytime the control rod i s withdrawn t o the "Full out" position in subsequent operation, I

c. Following malntenance on or modification t o the control rod or control rod drive system which could have affected the control rod t e g r 1 0 g the uncoupled control rod per Specificati-3.1.3.6,d the uncoupled rod's position shall be verffqed to have followed the control rod drive by neutron instrumentatjon (LPRM or TIP). I f the control blade can not be v e r i f i e d t o have followed the d r i v e out t o i t s final position, then the rod shall be completely inserted and the control rdd d i r e c t i o n a l valves disarmed as s t a t e d JAM161998 1IMERICK - UNIT 1 314 1-12 krrnhnath. l24

Section 3.3.7.2 (Deleted)

FROM THIS TECHNICAL CTION HAS BEEN RELOCATED TECHNICAL SPECIFICATIONS HROUGH 3 / 4 3-72 OF THIS SECTION HAVE BEEN INTENTIONALLY OMITTED.

gG 2 y 1994 LIMERICK - UNIT 1 314 3-68 Amendment No. 11, 4 6 , 7 5

Section 3/4.3.8 (Deleted)

THE INFORMATION FRON THIS TECHNICAL I FICAT IONSTOSECT1 SPECRELOCATED .I* - BEEN TEw TECH ICAC SPEC I F ICATIONS 3f4 3-111 HAS BEEN INTENTIONALLY OMITTED.

SE? 2 . 1 LIMERICK - UNIT 1 314 3-110 Amendment No. 100

REACTOR C C ; x A r ; i SYSTEM 3/4.4.3 REPLTOR COOLANT SYSTEM LEAKAGE LEAKAGE DFTECTION S YSTEMS 3.4.3.1 The f o l l o w i n g r e a c t o r coclant leakage detection systems s h a l l be OPFRAHLE :

a. The primary containment atmosphere gaseous r a d i o a c t i v i t y monitoring system,

b. The drywell f l o o r d r a i n sump f l o w monitoring system,

c. The drywell u n i t coolers condensate f l o w r a t e monitoring system, and

d. The primary containment pressure and temperature m o n i t o r i n g system.

A P P L I C A B I L I T Y : OPERATIONAL CONDITIONS 1, 2, and 3.*

• - The p r i m a r y containment gaseous r a d i o a c t i v i t y monitor i s not r e q u i r e d t o be operable u n t i l Operational Condition 2.

ACTIONS:

I A. With t h e primary containment atmosphere gaseous r a d i o a c t i v i t y moni t o r i n g system inoperable, analyze grab samples o f primary containment atmosphere a t l e a s t once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND restore primary containment atmosphere gaseous r a d i o a c t i v i t y monitoring system t o OPERABLE status w i t h i n 30 days.

B. With the d r y w e l l f l o o r d r a i n sump f l o w m o n i t o r i n g d r y w e l l f l o o r d r a i n sump f l o w monitoring system t o AN0 increase m o n i t o r i n g frequency o f d r y w e l l u n i t cooler condensate f l o w r a t e (SR 4.4.3.2.1.c) t o once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

A- case C. With t h e drywell u n i t coolers condensate f l o w r a t e AND t h e primary containment atmosphere gaseous r a d i o a c t i v i t y OPERABLE, perform a channel check o f the primary containment atmosphere gaseous r a d i o a c t i v i t y monitoring system (SR 4.4.3.1.a) once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

0. mary containment pressure and temperature moni t o r i n g system r e s t o r e t h e primary containment pressure and temperature monitoring ERABLE s t a t u s w i t h i n 30 days. NOTE: A l l other Tech Spec L i m i t i n q ce Rea. u i rement s associated w i t h t h e p r i m a r v containrnent pressure/tgmper a t u r e moni torincr S Y S tern s t i l l app l v . , A f f e c t e d Tech Spec Sec t i o n s include: 3/4. 3.7.5. 4.4.3.2.1. 3/4.6.1.6. a nd 3/4.6.1.7, mary containment atmosphere gaseous r a d i o a c t i v i t y monitoring system NO the drywell u n i t coolers condensate f l o w r a t e monitoring system r e s t o r e the primary containment atmosphere gaseous r a d i o a c t i v i t y stem t o OPERABLE status w i t h i n 30 days OR restore t h e drywell u n i t wc coolers condensate flow r a t e monitoring system t o OPERABLE status w i t h i n 30 days.

With t h e primary containment atmosphere gaseous r a d i o a c t i v i t y monitoring system inoperable, analyze grab samples o f primary Containment atmosphere a t least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

L I M E R I C K - UEIIT 1 3/4 4 - 8 Amendment U , 444, 169

3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ECCS - OPERATING L I M I T I N G CONDITION FOR OPERATION 3.5.1 The emergency core cooling systems s h a l l be OPERABLE with:

a. The core spray system (CSS) consisting o f two subsystems with each subsystem comprised of:

2. An OPERABLE o f taking suction from the the water through the spray sparger t o the reactor vessel.

b. The low pressure coolant i n j e c t i o n (LPCI) system o f t h e residual heat removal system consisting o f four subsystems with each subsystem comprised of:

1. One OPERABLE LPCI pump, and

2. An OPERABLE flow path capable o f t a k i n g suction from t h e suppression chamber and t r a n s f e r r i n g the water t o t h e reactor vessel.

C. The high pressure coolant i n j e c t i o n (HPCI) system consisting of:

1. One OPERABLE HPCI pump, and

2. An OPERABLE f l o w path capable o f t a k i n g suction from t h e suppression chamber and t r a n s f e r r i n g the water t o t h e reactor vessel.

d. The automatic depressurization system (ADS) w i t h a t l e a s t f i v e OPERABLE ADS valves.

APPLICABILITY : OPERATIONAL CONDITION 1, 2" ** #, and 3* ** ##.

• The HPCI system i s n o t required t o be OPERABLE when reactor steam dome pressure i s less than o r equal t o 200 psig.

• • The ADS i s not required t o be OPERABLE when the reactor steam dome pressure i s less t h a t or equal t o 100 psig.

1. See Special Test Exception 3.10.6.

1. 1. Two LPCI subsystems o f the RHR system may be inoperable i n t h a t they are aligned i n the shutdown cooling mode when reactor vessel pressure i s less than t h e RHR Shutdown cooling permissive setpoint.

CONTAINMENT SYSTEMS 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES 3.6.3 Each primary ainment i s o l a t i o n v rumentation l i n e excess f l o w check v a l a l l be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIQNS 1, 2, and 3.

ACTION :

a. With one or more o f t h e p r i m a r y containment i s o l a t i o n v a l v e s inoperable,**

m a i n t a i n a t l e a s t one i s o l a t i o n v a l v e OPERABLE i n each a f f e c t e d p e n e t r a t i o n t h a t i s open and w i t h i n 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> e i t h e r :

1. Restore t h e i n o p e r a b l e valve(s1 t o OPERABLE s t a t u s , o r

2. I s o l a t e each a f f e c t e d p e n e t r a t i o n by use o f a t l e a s t one de-a c t i v a t e d automatic v a l v e secured i n the i s o l a t e d p o s i t i o n ,

• or

3. I s o l a t e each a f f e c t e d p e n e t r a t i o n by use o f a t l e a s t one closed manual valve o r b l i n d flange."

Otherwise, be i n a t l e a s t HOT SHUTDOWN w i t h i n t h e n e x t 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and i n COLD SHUTDOWN w i t h i n t h e f o l l o w i n g 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. With one o r more o f t h e i n s t r u m e n t a t i o n l i n e excess f l o w check valves inoperable, o p e r a t i o n may c o n t i n u e and t h e p r o v i s i o n s o f S p e c i f i c a t i o n 3.0.3 a r e n o t a p p l i c a b l e p r o v i d e d t h a t w i t h i n 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> e i t h e r :

1. The inoperable v a l v e i s r e t u r n e d t o OPERABLE s t a t u s , o r

2. The instrument l i n e i s i s o l a t e d and the a s s o c i a t e d i n s t r u m e n t is decl ared inoperabl e.

Otherwise, be i n a t 7east HOT SHUTDOWN w i t h i n t h e n e x t 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and i n COLD SHUTDOWN w i t h i n t h e f o l l o w i n g 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. With one o r more scram d i s c h a r g e volume vent o r d r a i n v a l v e s inoperable, perform t h e a p p l i c a b l e a c t i o n s s p e c i f i e d i n S p e c i f i c a t i o n 3.1.3.1.

• I s o l a t i o n valves closed t o s a t i s f y these requirements may be reopened on an i n t e r m i t t e n t b a s i s under a d m i n i s t r a t i v e c o n t r o l .

• • Except f o r t h e scram discharge volume vent and d r a i n valves.

LIMERICK - UNIT 1 314 6 - 1 7 Amendment No. 29, 446, W , 169

J J

't DEC 2 0 1995 LIHERICK - UNIT 1 314 6-49 Amendment No. 23,105

THE INFORMATION FROM THIS TECHNICAL SPEC FICATIONS SECTION HAS BEEN RELOCATED TO THE&

c7Rm DEC 2 0 1995 LIMERICK - UNIT 1 314 6-51 Amendment No. 23,105

THE INFORMATION FROM THIS TECHNICAL SECTION HAS BEEN RELOCATED TO THE DEC 2 0 l9¶5 LIMERICK - UNIT 1 314 6-51a Amendment No. 23,105

PLANT SYSTEMS M l T I N G W I T I O N FOR OPFRATION (Continued)

ACTION: (Continued)

4. With t h r e e ESW pump/diesel generator p a i r s *

• i n o p e r a b l e ,

r e s t o r e a t l e a s t one i n o p e r a b l e ESW pump/diesel generator p a i r *

• t o OPERABLE s t a t u s w i t h i n 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, o r be i n a t l e a s t HOT SHUTDOWN w i t h i n t h e n e x t 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and i n COLD SHUTDOWN w i t h i n t h e f o l l o w i n g 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

5. W i t h f o u r ESW pump/diesel generator p a i r s *

• i n o p e r a b l e , r e s t o r e a t l e a s t one i n o p e r a b l e ESW pumpidiesel g e n e r a t o r p a i r *

• t o OPERABLE s t a t u s w i t h i n 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, o r be i n a t l e a s t HOT SHUTDOWN w i t h i n t h e n e x t 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and i n COLD SHUTDOWN w i t h i n t h e f o l l o w i n g 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. In OPERATIONAL CONDITION 4 o r 5: .

1. W i t h o n l y one emergency s e r v i c e water pump and i t s a s s o c i a t e d f l o w p a t h OPERABLE, r e s t o r e a t l e a s t two pumps w i t h a t l e a s t one f l o w p a t h t o OPERABLE s t a t u s w i t h i n 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> o r d e c l a r e t h e a s s o c i a t e d s a f e t y r e l a t e d equipment i n o p e r a b l e and t a k e t h e ACTION r e q u i r e d by S p e c i f i c a t i o n s 3.5.2 and 3.8.1.2.

C. I n OPERATIONAL CONDITION *

1. With o n l y one emergency s e r v i c e water pump and i t s a s s o c i a t e d f l o w p a t h OPERABLE, r e s t o r e a t l e a s t two pumps w i t h a t l e a s t one f l o w p a t h t o OPERABLE s t a t u s w i t h i n 7 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> o r v e r i f y adequate c o o l i n g remains a v a i l a b l e f o r t h e d i e s e l g e n e r a t o r s r e q u i r e d t o be OPERABLE o r d e c l a r e t h e a s s o c i a t e d d i e s e l g e n e r a t o r ( s 1 i n o p e r a b l e and t a k e t h e ACTION r e q u i r e d by S p e c i f i c a t i o n 3.8.1.2. The p r o v i s i o n s o f S p e c i f i c a t i o n 3.0.3 are not applicable.

4.7.1.2 A t l e a s t t h e above r e q u i r e d emergency s e r v i c e w a t e r system l o o p ( s )

s h a l l be demonstrated OPERABLE:

a. I n accordance w i t h t h e S u r v e i l l a n c e Frequency C o n t r o l Program by v e r i f y i n g t h a t each v a l v e (manual, power-operated, o r a u t o m a t i c ) t h a t I

i s n o t locked, sealed, o r o t h e r w i s e secured i n p o s i t i o n , i s i n i t s c o r r e c t p o s i t ion.

b. I n accordance w i t h t h e S u r v e i l l a n c e Frequency C o n t r o l Program by v e r i f y i ng t h a t :

I

1. Each automatic v a l v e a c t u a t e s t o i t s c o r r e c t p o s i t i o n on i t s a p p r o p r i a t e ESW pump s t a r t s i g n a l .

2. Each pump s t a r t s a u t o m a t i c a l l y when i t s associated d i e s e l generator s t a r t s .

• When h a n d l i n g i r r a d i a t e d f u e l i n t h e secondary containment.

• • An ESW pump/diesel g e n e r a t o r p a i r c o n s i s t s o f an ESW pump and i t s associated d i e s e l g e n e r a t o r . I f e i t h e r an ESW pump o r i t s associated d i e s e l generator becomes i n o p e r a b l e , then t h e ESW pump/diesel g e n e r a t o r p a i r i s inoperable.

LIMERICK - U N I T 1 3/4 7 - 4 Amendment No. 2J, 48, 74,186

ELECTRICAL muER SYnrWs .

LIMITING COM)ZTfON FOR OPERATION 3.8.1.2 As 0 mSnhme tha following A.C. electrical pow? sources shill h OPERABE:

1. One c h u f f bokrcHn the o f f s f k trmS.iSSh network and the onsf-Class lE distribution system,. and' l o 20 3.

APPLICABILITY:

I ACTIW:

am W i t h less thur the above required A.C. elcrctrfcal power sources OPERABLE, suspend W E ALTERATIOWS, W l f n g of irradiated furl i n t h e seconday containment, operations with (I potential f o r draining the mactOr vessel and cram oprrrtions o v w t)n spent fuel storr pool when fuel urWlhrr 813) s t a n d tlmmtn. In addltjon, u k n n OPERATIOlJAL ITI ION 5 with the water level less thur 22 fmt above r

the mutor pressure vessel f l a w , i m d i a t e l y - i n i t i a t e correct+ve action to -ston th r e q u i d powr sources to OPEMU status as soon as practical.

b. The pro~$sfonso f S p d f f U t i O n 3e0.3 am not 8pplhble.

SURVEfLUNCE REaoIRE?EMTS I

W h n handling fwrdirtad fwl i n the secondry totrtrimmnt.

LIERICK - UNIT 1

's-

Section 3/4.8.4.1 (Deleted)

SECTION PAGES 3/4 8-21 INTENTIONALLY OMITTED.

LIMERICK - UNIT 1 314 8-21 Amendment No. 32, 48, 31, 93 Jul 0 7 1995

INDEX SECTION DEFINITIONS ( C o n t i n u e d ) PAGE 1.20a LOW (POWER) T R I P SETPOINT (LTSP) ............................ 1-4 1.21 (DELETED) ................................................... 1-4 1.22 MEMBER(S) OF THE PUBLIC .................................... 1-4 1.22a MAPFAC( F) .(MAPLHGR FLOW FACTOR) .......................... 1-4 1.22b MAPFAC(P) .(POWER DEPENDENT MAPLHGR MULTIPLIER) ........... 1-4 1.23 MINIMUM CRITICAL POWER RATIO (MCPR) ........................ 1-4 1.24 OFFSITE DOSE CALCULATION MANUAL ............................ 1-4 1.25 OPERABLE .OPERABILITY ..................................... 1-4 1.26 OPERATIONAL CONDITION .CONDITION .......................... 1-5 1.27 PHYSICS TESTS ............................................... 1-5 1.28 PRESSURE BOUNDARY LEAKAGE .................................. 1-5 1.29 PRIMARY CONTAINMENT INTEGRITY .............................. 1-5 1.30 PROCESS CONTROL PROGWM .................................... 1-5 1.31 PURGE .PURGING ............................................ 1-6 1.32 RATED THERMAL POWER ........................................ 1-6 1.33 REACTOR ENCLOSURE SECONDARY CONTAINMENT INTEGRITY .......... 1-6 1.34 REACTOR PROTECTION SYSTEM RESPONSE T I EVENT ...........................................

RGIN ............................................ 1-7 1.41 SOURCE CHECK ............................................... 1-7 LIMERICK .UNIT 2 ii Amendment So . 11. 1 6 . 48 JAN 3 7 1995

INDEX A D M I N I S T R A T I V F CONTROl S SECTION PAGE 6.5.2 Deleted I Deleted .................................................... 6 - 9 I Deleted .................................................... 6-9 I Deleted ....................................................6 - 1 0 I Deleted .................................................... 6 - 1 0 I Deleted ....................................................6-10 I Deleted ....................................................6 - 1 0 I Deleted ....................................................6 - 1 0 I Deleted .................................................... 6 - 1 2 I 6.5.3 D e l e t e d ....................................................6 - 1 2 I 6.6 REPORTABLE EVENT ACT10............................................. 6-12a 6.7NLIMITVIOCATIQN............................................. 6-12a 6.8 PROC EDU RES AND PROGRAMS ............................................ 6-13 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS ............................................ 6-15 S t a r t u p Report ............................................. 6-15 Annual Reports ............................................. 6-15 Monthly O p e r a t i n g Reports .................................. 6-16 Annual R a d i o l o g i c a l Environmental O p e r a t i n g Report ......... 6 - 1 6

@nudl R a d i o a c t i v e E f f l u e n t Release Report ............. 6 - 1 7 CORE OPERATING LIMITS REPORTS .............................. 6-18a 6.9.2 SPECIAL REPORTS ............................................ 6-18a 6.10 DELETED ........................................................... 6-19 6.11 RADIATION PROTECTION PROGRAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 - 20 6.12 HIGH RADIATION AREA ............................................... 6-20 LIMERICK - U N I T 2 xxvi i Amendment No. 4, a,138

DFFINITIWS l O G I C SYSTFM FUNCTIONAL TEST 1.20 A LOGIC SYSTEM FUNCTIONAL TEST s h a l l be a t e s t o f a l l l o g i c components, i.e., a l l r e l a y s and c o n t a c t s , a l l t r i p u n i t s , s o l i d s t a t e l o g i c elements, e t c , o f a l o g i c c i r c u i t , from sensor through and i n c l u d i n g t h e actuated device, t o v e r i f y OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by any s e r i e s of s e q u e n t i a l , overlapping o r t o t a l system steps such t h a t t h e e n t i r e l o g i c system i s t e s t e d .

!OW (POWER) TRIP SETPOINT (LTSP) 1.20a The low power t r i p s e t p o i n t associated w i t h t h e Rod Block M o n i t o r (RBM) rod b l o c k t r i p s e t t i n g a p p l i c a b l e between 30% and 65% r e a c t o r thermal power.

1.21 (Deleted MEMBFR(S1 OF THF PUBLIC 1.22 MEMBER OF THE PUBLIC means any i n d i v i d u a l except when t h a t i n d i v i d u a l i s r e c e i v i n g an occupational dose. I 1

MA 1.22a A core f l o w dependent m u l t i p l i c a t i o n f a c t o r used t o f l o w b i a s t h e standard Maximum Average Planar L i n e a r Heat Generation Rate (MAPLHGR) l i m i t .

MAPFAC(P1-(POWER DEPENDENT MAPIHGR MULTIPLIER) 1.22b A core power dependent mu1t i p 1 i c a t i o n f a c t o r used t o power b i a s t h e standard Maximum Average Planar L i n e a r Heat Generation Rate (MAPLHGR) l i m i t .

MINIMUM CRITICAI POWER RATIO (MCPR) 1.23 The MINIMUM CRITICAL POWER RATIO (MCPR) s h a l l be t h e s m a l l e s t CPR which e x i s t s i n t h e core ( f o r each c l a s s o f f u e l ) . Associated w i t h t h e minimum c r i t i c a l power r a t i o i s a c o r e f l o w dependent (MCPR(F)) and core power dependent (MCPR( P ) ) m i nimurn c r i t i c a l power r a t i o .

OFFSITE DOSF CALCUIATION MANUAL 1.24 The OFFSITE DOSE CALCULATION MANUAL (ODCM) s h a l l c o n t a i n t h e methodology and parameters used i n t h e c a l c u l a t i o n o f o f f s i t e doses r e s u l t i n g from r a d i o a c t i v e gaseous and l i q u i d e f f l u e n t s , i n t h e c a l c u l a t i o n o f gaseous o f the Radiological a l s o c o n t a i n (1)

Environmental Mon o and l i q u i d e f f l u e n t m o r i n g a l a r m / t r i p s e t p o i n t s , and i n t h e conduct v i onmental M o n i t o r i n g Program. The ODCM s h a l l i o a c t i ve E f f l uent Control s and Radio1 o g i c a l g Programs r e q u i r e d by S e c t i o n 6.8.4 and ( 2 )

d e s c r i p t i o n s o f t h e i n f o r m a t i o n t h a t should be i n c l u d e d i n t h e Annual R a d i o l o g i c a l Environmental Operating and Annual R a d i o a c t i v e E f f l u e n t Release Reports r e q u i r e d by S p e c i f i c a t i o n s 6.9.1.7 and 6.9.1.8.

OPERABLE - OPERABILITY 1.25 A system, subsystem, t r a i n , component o r device s h a l l be OPERABLE o r have OPERABILITY when i t i s capable o f p e r f o r m i n g i t s s p e c i f i e d f u n c t i o n ( s ) and when a l l necessary a t t e n d a n t i n s t r u m e n t a t i o n , c o n t r o l s , e l e c t r i c a l power, c o o l i n g o r seal water, l u b r i c a t i o n o r o t h e r a u x i l i a r y equipment t h a t a r e r e q u i r e d f o r t h e system, subsystem, t r a i n , c c ~ ~ o n e n to,r d e v i c e t o perform i t s f u n c t i o n ( s 1 a r e a l s o capable o f p e r f o r m i n g t r r r e l a t e d support f u n c t i o n ( s 1 .

LIMERICK - UNIT 2 Amendment No. 44, %, 148

S e c t i o n 3.3.7.2 ( D e l e t e d )

FROM THIS TECHNICAL ION HAS BEEN RELOCATED CHNICAL SPECIFICATIONS PAGES 3 / 4 3-69 THROUGH 3 / 4 3-72 OF THIS SECTION HAVE BEEN INTENTIONALLY OMITTED.

LIMERICK - UNIT 2 314 3-68

Section 3/4.3.8 (Deleted)

- THE INFORMATION FROn THIS TECHNICAL HAS BEEN INTENTIONALLY OUInED.

SIP 2 1 1995 LIMERICK - UNIT 2 311 3-110 Amendment No. 64

REACTOR COOLANT SYSTEM 3/4.4,3 REACTOR COOLANT SYSTEM LEAKAGE LFAKAGE DETFCTION SYSTFMS 3.4.3.1 The fol'lowing r e a c t o r Coolant leakage d e t e c t i o n systems shall be OPERABLE:

a. The p r i m a r y containment atmosphere gaseous r a d i o a c t i v i t y m o n i t o r i n g system,

b. The d r y w e l l f l o o r d r a i n sump f l o w monitoring system,

c. The drywell u n i t coolers condensate f l o w r a t e monitoring system, and

d. The primary containment pressure and temperature monitoring system.

APPLICABILI TY: OPERATIONAL CONDITIONS 1, 2, and 3."

• - The primary containment gaseous r a d i o a c t i v i t y monitor i s n o t r e q u i r e d t o be operable u n t i l Operational C o n d i t i o n 2.

ACTIQNS:

I A. With the primary containment atmosphere gaseous r a d i o a c t i v i t y m o n i t o r i n g system inoperable, analyze grab samples o f primary containment atmosphere a t l e a s t once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND r e s t o r e p r i m a r y containment atmosphere gaseous r a d i o a c t i v i t y m o n i t o r i n g system t o OPERABLE s t a t u s w i t h i n 30 days.

B. With the d r y w e l l f l o o r d r a i n sump f l o w monitoring system d r y w e l l floor d r a i n sump f l o w m o n i t o r i n g system t o AND increase m o n i t o r i n g frequency o f d r y w e l l u n i t c o o l e r condensate f l o w r a t e (SR 4.4.3.2.1.c) t o once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

C. With the d r y w e l l u n i t c o o l e r s condensate f l o w r a t e m o n i t o r i n g s y s t e m W G 3 AND t h e primary containment atmosphere gaseous r a d i o a c t i v i t y m o n i t o r i n g system OPERABLE, perform a channel check o f the primary containment atmosphere gaseous r a d i o a c t i v i t y m o n i t o r i n g system (SR 4.4.3.1.a) once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

rimary containment pressure and temperature m o n i t o r i n g system r e s t o r e t h e primary containment pressure and temperature m o.n i.t o.r i n g ERABLE s t a t u s w i t h i n 30 days. Note: All o t h e r Tech SDec L i m i t i n q r a t i o n and Survei 11ance Reuui rernents assoc i a t e d with t h e g r i m a r v c ontainment pressure/temperature rnonitorinq S Y S tem s t i l l app IY. Affected Tech Spec Sections i n c l u d e : 3/4.3.7.5. 4.4.3.7.1. 3/4. 6.1.6. and 3/4.6.1. 7, r i m a r y containment atmosphere gaseous r a d i o a c t i v i t y m o n i t o r i n g system the d r y w e l l u n i t c o o l e r s condensate flow r a t e m o n i t o r i n g system t h e primary containment atmosphere gaseous r a d i o a c t i v i t y OPERABLE s t a t u s w i t h i n 30 days OR r e s t o r e t h e d r y w e l l u n i t coolers condensate f l o w r a t e m o n i t o r i n g system t o OPERABLE s t a t u s w i t h i n 30 days.

w i t h the primary containment atmosphere gaseous r a d i o a c t i v i t y m o n i t o r i n g system inoperable, analyze grab samples o f primary containment atmosphere a t l e a s t once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

LIMERICK - UNIT 2 3/4 4-8 Amendment No. 34, 1-83, 132

REACTOR COOLANT SYSTEM ACTIONS ( C o n t i n u e d )

, . W i t h any o t h e r two o r more l e a k d e t e c t i o n systems i n o p e r a b l e o t h e r t h a n ACTION E above OR w i t h r e q u i r e d A c t i o n s and a s s o c i a t e d C o m p l e t i o n Time o f ACTIONS A, B ,

C , D o r E n o t met, b e i n HOT SHUTDOWN w i t h i n 12 h o u r s AND i n COLD SHUTDOWN w i t h i n t h e n e x t 24 h o u r s .

SURVEILLANCE REQUIREMENTS -~

4.4.3.1 The r e a c t o r c o o l a n t system l e a k a g e d e t e c t i o n systems s h a l l be d e m o n s t r a t e d operable by:

a. P e r f o r m a CHANNEL CHECK o f t h e p r i m a r y c o n t a i n m e n t atmosphere gaseous r a d i o a c t i v i t y m o n i t o r i n g system i n accordance w i t h t h e S u r v e i 11 ance Frequency C o n t r o l Program.

b. P e r f o r m a CHANNEL FUNCTIONAL TEST qui red leakage d e t e c t i o n i n s t r u m e n t a t i o n i n accordance w i t h he S u r v e i l l a n c e Frequency C o n t r o l Program. T h i s does n o t a p p l y t o c o n t a i n m e n t p r e s s u r e and t e m p e r a t u r e m o n i t o r i n g system.

c. P e r f o r m a CHANNEL CALIBRATION o f r e q u i r e d l e a k a g e d e t e c t i o n i n s t r u m e n t a t i o n i n accordance w i t h t h e S u r v e i 11 ance Frequency C o n t r o l Program. T h i s does I n o t a p p l y t o c o n t a i n m e n t p r e s s u r e and t e m p e r a t u r e m o n i t o r i n g system.

d. Monitor primary containment pressure & NJ primary containment temperature i n accordance w i t h t h e S u r v e i 11 ance Frequency C o n t r o l Program. I LIMERICK - UNIT 2 3/4 4-8a Amendment No. 1-Bc3,147

3 / 4 3 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ECCS - OPERATING LIMITING CONDITION FOR OPERATION 3.5.1 The emergency core cool iig systems shall be OPERABLE with:

a. The core spray system (CSS) consisting of two subsystems with each subsystem comprised of:

suction from the the water through the spray sparger to the reactor vessel.

b. The low pressure coolant injection (LPCI) system o f the residual heat removal system consisting o f four subsystems with each subsystem comprised of:

1. One OPERABLE LPCI pump, and

2. An OPERABLE f l o w path capable of taking suction from the suppression chamber and transferring the water to the reactor vessel.

c. The high pressure coolant injection (HPCI) system consisting of:

1. One OPERABLE HPCI pump, and

2. An OPERABLE flow path capable o f taking suction from the suppression chamber and transferring the water to the reactor vessel .

d. The automatic depressurization system (ADS) with at least five OPERABLE ADS valves.

APPLICABILITY: OPERATIONAL CONDITION 1, 2* ** #, and 3" ** X f .

• The HPCI system is not required to be OPERABLE when reactor steam dome pressure is less than or equal to 200 psig.

• • The ADS is not required to be OPERABLE when the reactor steam dome pressure is less that or equal to 100 psig.

%See Special Test Exception 3.10.6.

1. 1. Two LPCI subsystems o f the RHR system may be inoperable in that they are aligned in the shutdown cooling mode when reactor vessel pressure is less than the RHR Shutdown cooling permissive setpoint.

Amendment No. %, 92 LIMERICK - UNIT 2 314 5-1 .EIoV 1 6 1998

CONTAINMENT SYSTEMS DRYWELL AVERAGE A I R TEMPERATURE LIMITING C O N D I T I O N FOR OPERATION 3.6.1.7 D r y w e l l average a i r temperature s h a l l n o t exceed 1 4 5 " e d,/crle APPLICABILITY: OPERATIONAL CONDITIONS I , 2, and 3.

ACTION

- 0 abbh With t h e d r y w e l l average a i r temperature g r e a t e r t h a n 145"@reduce the average a i r t e m p e r a t u r e t o w i t h i n t h e l i m i t w i t h i n 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> o r be i n a t l e a s t HOT SHUTDOWN w i t h i n t h e n e x t 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and i n COLD SHUTDOWN w i t h i n t h e f o l l o w i n g 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.1.7 The d r y w e l l average a i r t e m p e r a t u r e s h a l l be t h e v o l u m e t r i c average o f t h e temperatures a t t h e f o l l o w i n g l o c a t i o n s and s h a l l be determined t o be w i t h i n t h e l i m i t i n accordance w i t h t h e S u r v e i l l a n c e Frequency C o n t r o l Program: 1 Approximate Number o f Elevation I n s t a l l e d Sensors*

a. 330 ' 3

b. 320 ' 3 C. 260 ' 3

d. 248' 6

• A t l e a s t one r e a d i n g f r o m each e l e v a t i o n i s r e q u i r e d f o r a v o l u m e t r i c average a i r ternperatur u r r e n t o p e r a t i ng c y c l ent duration t o a l l 0 c o o l e r f a n r e p a i r s , whichever comes f i r s t .

LIMERICK - U N I T 2 3/4 6 - 1 0 Amendment No. 424, 345, 1 4 7

CONTAINMENT SYSTEMS 3 / 4 . 6 . 3 P R I M A R Y CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3 Each p r i m a r y containment i s o l a t i o n rumentation l i n e excess f l o w check v a l v e s h a l l be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACT ION :

a. With one o r more o f t h e p r i m a r y containment i s o l a t i o n valves inoperable,**

m a i n t a i n a t l e a s t one i s o l a t i o n valve OPERABLE i n each a f f e c t e d p e n e t r a t i o n t h a t i s open and w i t h i n 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> e i t h e r :

1. Restore the i n o p e r a b l e v a l v e ( s ) t o OPERABLE s t a t u s , o r

2. I s o l a t e each a f f e c t e d p e n e t r a t i o n by use o f a t l e a s t one de-a c t i v a t e d automatic v a l v e secured i n the i s o l a t e d p o s i t i o n ,

• o r

3. I s o l a t e each a f f e c t e d p e n e t r a t i o n by use o f a t l e a s t one c l o s e d manual v a l v e o r b l i n d f l a n g e .

• Otherwise, be i n a t l e a s t HOT SHUTDOWN w i t h i n t h e n e x t 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and i n COLD SHUTDOWN w i t h i n t h e f o l l o w i n g 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. With one o r more o f t h e i n s t r u m e n t a t i o n l i n e excess f l o w check valves inoperable, o p e r a t i o n may continue and t h e p r o v i s i o n s of S p e c i f i c a t i o n 3.0.3 are n o t a p p l i c a b l e provided t h a t w i t h i n 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> e i t h e r :

1. The inoperable v a l v e i s r e t u r n e d t o OPERABLE s t a t u s , o r

2. The instrument l i n e i s i s o l a t e d and t h e associated i n s t r u m e n t i s declared i n o p e r a b l e .

Otherwise, be i n a t l e a s t HOT SHUTDOWN w i t h i n t h e n e x t 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and i n COLD SHUTDOWN w i t h i n t h e f o l l o w i n g 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. With one o r more scram discharge volume vent o r d r a i n valves i n o p e r a b l e ,

perform t h e a p p l i c a b l e a c t i o n s s p e c i f i e d i n S p e c i f i c a t i o n 3.1.3.1.

• I s o l a t i o n valves closed t o s a t i s f y these requirements may be reopened on an i n t e r m i t t e n t b a s i s under a d m i n i s t r a t i v e c o n t r o l .

• • Except f o r the scram discharge volume vent and d r a i n valves.

LIMERICK - UNIT 2 3/4 6 - 1 7 Amendment No. W , W , 132

THE INFORMATION FROM THIS TECHNICAL SPEC SECTION HAS BEEN RELOCATED TO THE LIMERICK - UNIT 2 314 6-49 Amendment No. 69 DEC 2 0 895

THE INFORMATION FROM THIS TECHNICAL SP SECTION HAS BEEN RELOCATED TO THE LIMERICK - UNIT 2 3/4 6-51 Amendment No. 6 9 DEC 2 0 1995

THE INFORMATION FROM THIS TECHNICAL SPECIFICATIONS SECTION HAS BEEN RELOCATED TO TH LIMERICK - UNIT 2 314 6-51a Amendment No. 69 DEC 2 0 t995

PLANT SYSTEMS 3/4.7.2 CONTROL ROOM EMERGENCY FRESH A I R SUPPLY SYSTEM - COMMON SYSTEM LIMITING CONDITION FOR OPERATION 3.7.2 Two independent c o n t r o l room emergency f r e s h a i r supply system subsystems s h a l l be OPERABLE.

APPLICABILITY: A l l OPERATIONAL CONDITIONS and when RECENTLY IRRADIATED FUEL i s b e i n g handled i n t h e secondary containment, o r d u r i n g o p e r a t i o n s w i t h a p o t e n t i a l f o r d r a i n i n g t h e reactor vessel.

ACTION :

a. I n OPERATIONAL CONDITION 1, 2, o r 3:

1. With t h e U n i t 1 d i e s e l g e n e r a t o r f o r one c o n t r o l room emergency f r e s h a i r supply subsystem i n o p e r a b l e f o r more t h a n 30 days, be i n a t l e a s t HOT SHUTDOWN w i t h i n t h e n e x t 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and i n COLD SHUTDOWN w i t h i n t h e f o l l owing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2. W i t h one c o n t r o l room emergency f r e s h a i r s u p p l y subsystem i n o p e r a b l e , r e s t o r e t h e i n o p e r a b l e subsystem t o OPERABLE s t a t u s w i t h i n 7 days, o r be i n a t l e a s t HOT SHUTDOWN w i t h i n t h e n e x t 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and i n COLD SHUTDOWN w i t h i n t h e f o l l o w i n g 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3. W i t h one c o n t r o l room emergency f r e s h a i r s u p p l y subsystem i n o p e r a b l e and t h e o t h e r c o n t r o l room emergency f r e s h a i r s u p p l y subsystem w i t h an i n o p e r a b l e U n i t 1 d i e s e l g e n e r a t o r , r e s t o r e t h e i n o p e r a b l e subsystem t o OPERABLE s t a t u s or r e s t o r e t h e U n i t 1 d i e s e l g e n e r a t o r t o OPERABLE s t a t u s w i t h i n 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, o r be i n a t l e a s t HOT SHUTDOWN w i t h i n t h e n e x t 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and i n COLD SHUTDOWN w i t h i n t h e f o l l o w i n g 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4. With t h e U n i t 1 d i e s e l g e n e r a t o r s f o r b o t h c o n t r o l room emergency f r e s h a i r supply subsystems i n o p e r a b l e f o r more t h a n 72 h o u r s ,

be i n a t l e a s t HOT SHUTDOWN w i t h i n t h e n e x t 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and i n COLD SHUTDOWN w i t h i n t h e f o l 1owi ng 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. I n OPERATIONAL CONDITION 4, 5 o r when RECENTLY IRRADIATED FUEL i s b e i n g handled i n t h e secondary containment, o r d u r i n g o p e r a t i o n s w i t h a p o t e n t i a1 f o r d r a i n i n g t h e r e a c t o r vessel :

1. W i t h one c o n t r o l room emergency f r e s h a i r s u p p l y subsystem i n o p e r a b l e , r e s t o r e t h e i n o p e r a b l e subsystem t o OPERABLE s t a t u s w i t h i n 7 days, o r i n i t i a t e and m a i n t a i n o p e r a t i o n o f t h e OPERABLE subsystem i n t h e r a d i a t i o n i s o l a t i o n mode o f o p e r a t i o n .

dd&

2. With b o t h 4 & & & t r o l room emergency f r e s h a i r s u p p l y subsystem inoperabl e, suspend hand1 ing o f RECENTLY IRRADIATED FUEL in t h e I secondary containment and o p e r a t i o n s w i t h a p o t e n t i a l f o r d r a i n i n g t h e r e a c t o r v e s s e l . The p r o v i s i o n s o f S p e c i f i c a t i o n 3.0.3 a r e n o t appl icab1 e.

LIMERICK - UNIT 2 3/4 7-6 Amendment No. 432, 146

• 'ELECTRICALPOWER SYSTEMS A.C. SOURCES - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a. One -ciI?cuft between 4he-offsite .transini-ssion network and the onsite Class lE distribution systm, and -

b. Two diesel generators each wfth:

1. A day fuel tank containing a minimum o f 200 gallons o f fuel.

2. A fuel storage system containing a ainimm o f 33,500 gallons o f fuel.

3. A fuel transfer pump.

APPLICABILIfY: OPERATIONAL CONDITIONS 4, 5, and *.

ACTION:

a. With less than the above required A.C. electrical power sources OPERABLEs suspend CORE ALTERATIONS, handling o f irradiated fuel i n the secondary containment, operations with a potential f o r draining the reactor vessel and crane operations over the spent fuel storage pool when fuel a s s W l i e s are stored therein. In addition, when i n OPERATIONAL CONDITION 5 with the water level less than 22 feet above the reactor pressure vessel. flange, immediately i n i t i a t e corrective action to restore the required power sources to OPERABLE status as soon as practical.

b. The provisions o f Specification 3.0.3 are mot applicable.

SURVEILLANCE REQUIREHENTS 4.8.1.2 A t least the above required A.C. electrical Suwei 11anct Requirements q h e n hand1ing irradfated fuel i n the secondary contai m n t .

LIMERICK = UNIT 2 314 8-9 M625- .

Section 3/4 8.4.1 (Deleted) 7

/flH THE INFORMATION FROM TH AL SPECIFICATION SECTION HAS BEEN RELOCATED TO TH TECHNICAL SPECIFICATIONS PAGES 3/4 8-21 THROUGH F THIS SECTION HAVE BEEN INTENTIONALLY OMITTED.

LIMERICK - UNIT 2 314 8-21 Amendment No. 34, 57 Jut 0 7 1995