RS-19-017, Application to Remove the Table of Contents from Technical Specifications and Place It Under Licensee Control
| ML19165A252 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Peach Bottom, Nine Mile Point, Byron, Braidwood, Limerick, Ginna, Quad Cities, FitzPatrick, LaSalle  |
| Issue date: | 06/14/2019 |
| From: | Simpson P Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RS-19-017 | |
| Download: ML19165A252 (119) | |
Text
4300 Winfield Road Warrenville, IL 60555 Exelon Generation 630 65 7 2000 Office RS-19-017 June 14, 2019 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457 Byron Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249 James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 NRC Docket No. 50-333 R.E. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18 NRC Docket No. 50-244 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-37 4 Limerick Generating Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352 and 50-353 Nine Mile Point Nuclear Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-63 and NPF-69 NRC Docket Nos. 50-220 and 50-410 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265 10 CFR 50.90
June 14, 2019 U.S. Nuclear Regulatory Commission Page 2
Subject:
Application to Remove the Table of Contents from Technical Specifications And Place it Under Licensee Control In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGC), requests an amendment to Renewed Facility Operating Licenses Nos. NPF-72 and NPF-77 for Braidwood Station, Units 1 and 2, Renewed Facility Operating Licenses Nos. NPF-37 and NPF-66 for Byron Station, Units 1 and 2, Renewed Facility Operating Licenses Nos. DPR-19 and DPR-25 for Dresden Nuclear Power Station, Units 2 and 3, Renewed Facility Operating License No. DPR-59 for James A.
FitzPatrick Nuclear Power Plant, Renewed Facility Operating License No. DPR-18 for R.E.
Ginna Nuclear Power Plant, Renewed Facility Operating Licenses Nos. NPF-11 and NPF-18 for LaSalle County Station, Units 1 and 2, Renewed Facility Operating Licenses Nos. NPF-39 and NPF-85 for Limerick Generating Station, Units 1 and 2, Renewed Facility Operating Licenses Nos. DPR-63 and NPF-69 for Nine Mile Point Nuclear Station, Units 1 and 2, Renewed Facility Operating Licenses Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station, Units 2 and 3, and Renewed Facility Operating Licenses Nos. DPR-29 and DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2. The proposed amendment would remove the Table of Contents (TOC) from the Technical Specifications (TS) and place it under licensee control. provides the evaluation for the proposed change. Attachment 2 provides the existing TS pages marked up to show the proposed change.
The proposed change has been reviewed by the Plant Operations Review Committees at each station in accordance with the requirements of the EGC Quality Assurance Program.
EGC requests approval of the proposed change by December 31, 2019. Once approved, the amendment shall be implemented within 60 days.
In accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"
paragraph (b), EGC is notifying the State of Illinois, State of New York, State of Pennsylvania, and the State of Maryland of this application for license amendment by transmitting a copy of this letter and its attachments to the designated State Officials.
June 14, 2019 U.S. Nuclear Regulatory Commission Page 3 There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mrs. Linda M. Palutsis at (630) 657-2821.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 14th day of June 2019.
R(decttu11y,
{~~
Manager-Licensing Attachments:
- 1. Description and Assessment
- 2. Markup of Proposed Technical Specifications Pages cc:
NRG Regional Administrator, Region I NRG Regional Administrator, Region Ill NRG Senior Resident Inspector - Braidwood Station NRG Senior Resident Inspector - Byron Station NRG Senior Resident Inspector - Dresden Nuclear Power Station NRG Senior Resident Inspector -James A. FitzPatrick Nuclear Power Plant NRG Senior Resident Inspector - R.E. Ginna Nuclear Power Plant NRG Senior Resident Inspector - LaSalle County Station NRG Senior Resident Inspector - Limerick Generating Station NRG Senior Resident Inspector - Nine Mile Point Nuclear Station NRG Senior Resident Inspector - Peach Bottom Atomic Power Station NRG Senior Resident Inspector - Quad Cities Nuclear Power Station Illinois Emergency Management Agency-Division of Nuclear Safety A.L. Peterson, NYSERDA Rich Janati, PADEP-BNR S.T. Gray, State of Maryland
ATTACHMENT 1 Description and Assessment 1.0
SUMMARY
DESCRIPTION The proposed amendment would remove the Table of Contents (TOC) from the Technical Specifications (TS) and place it under licensee control.
2.0 DETAILED DESCRIPTION In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGC), requests an amendment to Renewed Facility Operating Licenses Nos. NPF-72 and NPF-77 for Braidwood Station, Units 1 and 2, Renewed Facility Operating Licenses Nos. NPF-37 and NPF-66 for Byron Station, Units 1 and 2, Renewed Facility Operating Licenses Nos. DPR-19 and DPR-25 for Dresden Nuclear Power Station, Units 2 and 3, Renewed Facility Operating License No. DPR-59 for James A.
FitzPatrick Nuclear Power Plant, Renewed Facility Operating License No. DPR-18 for R.E.
Ginna Nuclear Power Plant, Renewed Facility Operating Licenses Nos. NPF-11 and NPF-18 for LaSalle County Station, Units 1 and 2, Renewed Facility Operating Licenses Nos. NPF-39 and NPF-85 for Limerick Generating Station, Units 1 and 2, Renewed Facility Operating Licenses Nos. DPR-63 and NPF-69 for Nine Mile Point Nuclear Station, Units 1 and 2, Renewed Facility Operating Licenses Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station, Units 2 and 3, and Renewed Facility Operating Licenses Nos. DPR-29 and DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2. The proposed amendment would remove the TOC from the TS and place it under licensee control.
Following the approval of this license amendment request, responsibility for maintenance and issuance of updates to the TS TOC will transfer from the Nuclear Regulatory Commission (NRC) to EGC. The TOC will no longer be included in the NRC issued TS and as such will no longer be part of the TS (Appendix A to the Operating License).
3.0 TECHNICAL EVALUATION
The TOC does not meet the criteria specified in 10 CFR 50.36 requiring its inclusion within a plant's TS. 10 CFR 50.36(b) states:
Each license authorizing operation of a production or utilization facility of a type described in § 50.21 or§ 50.22 will include technical specifications. The technical specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to § 50.34.
The results of EGC review indicates that the TS TOC was not listed in the regulation as one of the categories listed in 10 CFR 50.36(c).
Additionally, the "Writer's Guide for Plant-Specific Improved Technical Specifications" (ITS)
(Reference 1) was reviewed for guidance. The writer's guide refers to the TOC as "Technical Specification Front Matter," which also includes the Title Page and List of Effective Pages. The Page 1
ATTACHMENT 1 Description and Assessment writer's guide describes the TS Front Matter as not part of the TS. Additionally, the writer's guide describes the TS content as starting with Chapter 1, "Use and Application."
A TOC for the TS will be maintained under EGC control. The TOC will be issued by EGC in conjunction with the implementation of NRG-approved TS amendments that alter the TOC.
4.0 REGULATORY ANALYSIS
4.1 Applicable Regulatory Requirements/Criteria 10 CFR 50.36(a)(1) states:
Each applicant for a license authorizing operation of a production or utilization facility shall include in his application proposed technical specification in accordance with the requirements of this section. A summary statement of the bases or reasons for such specifications, other than those covering administrative controls, shall also be included in the application, but shall not become part of the technical specification.
Like the TS Bases, the TOC does not meet the criteria specified in 10 CFR 50.36 for inclusion within a plant's TS.
EGC has evaluated this change against the applicable regulatory requirements as described above. Based on this, there is reasonable assurance that the health and safety of the public, following approval of this change will remain unaffected.
4.2 Precedent Point Beach Nuclear Plant License Amendment Nos. 245 and 249 were issued on October 11, 2011 (Reference 2).
Calvert Cliffs Nuclear Power Plant License Amendment Nos. 293 and 269 were issued on September 21, 2009 (Reference 3).
Monticello Nuclear Generating Plant License Amendment No. 152 was issued on November 8, 2007 (Reference 4 ).
4.3 No Significant Hazards Consideration Determination Analysis In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGC), requests an amendment to Renewed Facility Operating Licenses Nos. NPF-72 and NPF-77 for Braidwood Station, Units 1 and 2, Renewed Facility Operating Licenses Nos. NPF-37 and NPF-66 for Byron Station, Units 1 and 2, Unit 1, Renewed Facility Operating Licenses Nos. DPR-19 and DPR-25 for Dresden Nuclear Power Station, Units 2 and 3, Renewed Facility Operating License No. DPR-59 for James A. FitzPatrick Nuclear Power Plant, Renewed Facility Operating License No. DPR-18 for R.E. Ginna Nuclear Power Plant, Renewed Facility Operating Licenses Nos. NPF-11 and NPF-18 for LaSalle County Station, Units 1 and 2, Renewed Facility Operating Licenses Nos. NPF-Page 2
ATTACHMENT 1 Description and Assessment 39 and NPF-85 for Limerick Generating Station, Units 1 and 2, Renewed Facility Operating Licenses Nos. DPR-63 and NPF-69 for Nine Mile Point Nuclear Station, Units 1 and 2, Renewed Facility Operating Licenses Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station, Units 2 and 3, and Renewed Facility Operating Licenses Nos. DPR-29 and DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2. The proposed amendment would remove the Table of Contents (TOC) from the Technical Specifications (TS) and place it under licensee control.
EGC has evaluated the proposed change against the criteria of 10 CFR 50.92(c) to determine if the proposed change results in any significant hazards. The following is the evaluation of each of the 10 CFR 50.92(c) criteria:
- 1.
Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The proposed amendment is administrative and affects control of a document, the TOC, listing the specifications in the plant TS. Transferring control from the NRC to EGC does not affect the operation, physical configuration, or function of plant equipment or systems. The proposed amendment does not impact the initiators or assumptions of analyzed events; nor does it impact the mitigation of accidents or transient events.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2.
Does the proposed change create the possibility of a new or different kind of accident from any previously evaluated?
Response: No The proposed change does not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or a change in the methods governing normal plant operation. The proposed change does not alter any assumptions made in the safety analysis.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
- 3.
Does the proposed change involve a significant reduction in a margin of safety?
Response: No The proposed change is administrative. The TOC is not required by regulation to be in the TS. Removal does not impact any safety assumptions or have the potential to reduce a margin of safety. The proposed change involves a transfer of control of the TOC from the NRC to EGC. No change in the technical content of the TS is involved.
Page 3
ATTACHMENT 1 Description and Assessment Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, EGC 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.
4.4 Conclusions 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 Commission's 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.
5.0 ENVIRONMENTAL EVALUATION The proposed amendment is confined to changes to recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(10). Therefore, pursuant to 10 CFR 51.22(b ), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
6.0 REFERENCES
- 1. Technical Specifications Task Force, TSTF-GG-05-01, "Writer's Guide for Plant-Specific Improved Technical Specifications," dated June 2005
- 2. Letter from Terry A. Beltz (U.S. NRC) to Mr. Larry Meyer (NextEra), "Point Beach Nuclear Plant, Units 1 and 2 - Issuance of Amendment RE: Request to Remove the Table of Contents from the Technical Specifications," dated October 11, 2011 (ML112640016)
- 3. Letter from Douglas V. Pickett (U.S. NRC) to Mr. James A. Spina (CCNPP), "Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 - Amendment RE: Request to Remove the Table of Contents from the Technical Specifications," dated September 21, 2009 (ML092120042)
- 4. Letter from Peter S. Sam (U.S. NRC) to Timothy J. O'Connor (NMC), "Monticello Nuclear Generating Plant-Issuance of Amendment RE: Removal of the Table of Contents Out of the Technical Specifications," dated November 8, 2007 (ML072960159)
Page4
ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.1 Braidwood Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-72 and NPF-77 Revised Technical Specification Pages i
ii iii iv
TABLE OF CONTENTS TECHNICAL SPECIFICATIONS
-+/---;{}
USE AND APPLICATION
~
Definitions.......................................... 1.1 1
~
Logical Connectors................................... 1. 2 1
-+/---: CoFRpl eti on Ti FRes..................................... 1. 3 1
+/-A Frequency............................................ 1. 4 1 b-0 SAFETY LIMITS ( SLs)
~
SLs................................................. 2.0 1 +/-
SL Viol ati ens........................................ 2. 0 1 -;-Q.
LH4ITHJG CONDITIO~J FOR OPERATION ( LCO) MJD SURVEILLANCE REQUIREMENT CSR) APPLICABILITY....................... 3.0 1 -;-}
REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDO't.JN MARG rn ( Srn4)................................ 3.1.1 1 3.1.2 Core Reactivity...................................... 3.1.2 1 3.1. 3
~4oderator TeFRperature Coefficient OffC).............. 3.1. 3 1 3.1.4 Rod Group AlignFRent LiFRits........................... 3.1.4 1 3.1.5 Shutdmm Bank Insertion LiFRits....................... 3.1.5 1 3.1.6 Control Bank Insertion LiFRits........................ 3.1.6 1 3.1.7 Rod Position Indication.............................. 3.1.7 1 3.1.8 PHYSICS TESTS Exceptions MODE 2...................... 3.1.8 1 4 POWER DI STRI BUTI mJ LIM ITS 3.2.1 Heat Flux Hot Channel Factor (Ft!(Z))................. 3.2.1 1
- 3. 2. 2 Nuclear Enthal PJ' Rise Hot Channel Factor CF!+)........ 3. 2. 2 1 3.2.3 AXIAL FLUX DIFFERENCE CAFD)......................... 3.2.3 1 3.2.4 QUADRANT POWER TILT RATIO (QPTR)..................... 3.2.4 1 3.2.5 Departure froFR Nucleate Boiling Ratio CDNBR)......... 3.2.5 1
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INSTRUMENTATION 3.3.1 Reactor Trip SJ'steFR CRTS) InstruFRentation............ 3.3.1 1
- 3. 3. 2 Engineered Safety Feature Actuation SysteFR (ESFAS) InstruFRentation.......................... 3.3.2 1 3.3.3 Post Accident Monitoring (PAM) InstruFRentation....... 3.3.3 1
- 3. 3. 4 ReFRote Shutdmm SJ'steFR............................... 3. 3. 4 1 3.3.5 Loss of Pml'er CLOP) Diesel Generator CDC) Start I nstruFRentati on.................................. 3. 3. 5 1 3.3.6 ContainFRent Ventilation Isolation InstruFRentation.... 3.3.6 1
- 3. 3. 7 Control RooFR Ventilation (VG) Filtration SJ'steFR Actuation InstruFRentation........................ 3.3.7 1 3.3.8 Fuel Handling Building Exhaust Filter PlenuFR (FHB)
Ventilation SysteFR Actuation InstruFRentation.... 3.3.8 1 3.3.9 Boron Dilution Protection SJ'steFR (BOPS).............. 3.3.9 1 BRAIDWOOD UN ITS 1 & 2 AFRendFRent 110
TABLE OF CONTE~JTS TECHNICAL SPECIFICATIONS -:-4 3.4.1 3.4.2 3.4.3 3.4.4 3.4.5 3.4.6 3.4.7 3.4.8 3.4.9 3.4.10 3.4.11 3.4.12 3.4.13 3.4.14 3.4.15 3.4.16 3.4.17 3.4.18 3.4.19 -; 3. 5. 1 3.5.2 3.5.3 3.5.4 3.5.5
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3.6.1 3.6.2 3.6.3 3.6.4 3.6.5 3.6.6 3.6.7 3.6.8
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3.7.1 3.7.2 3.7.3 3.7.4 3.7.5 3.7.6 REACTOR COOLANT SYSTrn (RCS)
RCS Pressure, Tefflperature, and Fl ml' Departure froffl Nucleate Boiling CDNB) Lifflits............... 3.4.1 1 RCS Miniffluffl Tefflperature for Criticality.............. 3.4.2 1 RCS Pressure and Tefflperature CP/ T) Lifflits............ 3.4.3 1 RCS Loops MODES 1 and 2.............................. 3.4.4 1 RCS Loops MODE 3..................................... 3.4.5 1 RCS Loops MODE 4..................................... 3.4.6 1 RCS Loops MODE 5, Loops Filled....................... 3.4.7 1 RCS Loops MODE 5, Loops Not Filled................... 3.4.8 1 Pressurizer.......................................... 3.4.9 1 Pressurizer Safety Valves............................ 3.4.10 1 Pressurizer Pml'er Operated Relief Valves EPORVs)..... 3.4.11 1 Lm,* Tefflperature Overpressure Protection E LTOP)
Systeffl........................................... 3.4.12 1 RCS Operational LEAKAGE.............................. 3.4.13 1 RCS Pressure Isolation Valve EPIV) Leakage........... 3.4.14 1 RCS Leakage Detection Instrufflentation............... 3.4.15 1 RCS Specific Activity................................ 3.4.16 1 RCS Loop Isolation Valves............................ 3.4.17 1 RCS Loops Isolated................................... 3. 4.18 1 Steaffl Generator (SC) Integrity....................... 3.4.19 1 i EMERGENCY CORE COOLING SYSTEMS (EGGS)
Accufflul a tors......................................... 3. 5.1 1 EGGS Operating....................................... 3.5.2 1 EGGS ShutdO'oi'n........................................ 3. 5. 3 1 Refueling 'tJater Storage Tank ER'tJST).................. 3.5.4 1 Seal Injection Flml'.................................. 3.5.5 1 CONTAINMENT SYSTEMS Genta i nfflent.......................................... 3. 6. 1 1 Contai nfflent Air Locks................................ 3. 6. 2 1 Containfflent Isolation Valves......................... 3.6.3 1 Containfflent Pressure................................. 3.6.4 1 Containfflent Air Tefflperature.......................... 3.6.5 1 Genta i nfflent Spray and Cooling SJ*steffls................ 3. 6. 6 1 Spray Additive Systeffl................................ 3. 6. 7 1 E Deleted)............................................ 3. 6. 8 1 PLANT SYSTEMS
~4ain Steaffl Safety Valves CMSSVs)..................... 3.7.1 1 Main Steaffl Isolation Valves EMSIVs).................. 3.7.2 1 Secondary Specific Activity.......................... 3. 7. 3 1 Steaffl Generator ESG) Pmi'er Operated Relief Valves CPORVs)................................... 3.7.4 1 Au><il i a ry Feed*,wter EAF) Systeffl...................... 3. 7. 5 1 Condensate Storage Tank (CST)........................ 3.7.6 1 BRAIDWOOD UN ITS 1 & 2 Afflendfflent 144
TABLE OF CONTENTS TECHNICAL SPECIFICATIONS
~
3.7.7 3.7.8 3.7.9 3.7.10 3.7.11 3.7.12 3.7.13 3.7.14 3.7.15 3.7.16
~
3.8.1 3.8.2 3.8.3 3.8.4 3.8.5 3.8.6 3.8.7 3.8.8 3.8.9 3.8.10 PLANT SYSTEMS (continued)
CoFRponent Cool i ng Water CCC) SJ'steFR.................. 3. 7. 7 1 Essential Service Water CSX) SJ'steFR.................. 3.7.8 1 UltiFRate Heat Sink CUHS)............................. 3.7.9 1 Control RooFR Ventilation C VG) Filtration SJ'steFR...... 3. 7.10 1 Control RooFR Ventilation CVC) TeFRperature Cont rel SysteFR................................... 3. 7.11 1 Nonaccessible Area Exhaust Filter PlenuFR Ventilation SJ'steFR............................... 3. 7.12 1 Fuel Handling Building Exhaust Filter PlenuFR C FHB) Ventilation SysteFR......................... 3. 7.13 1 Spent Fuel Pool Water Level.......................... 3.7.14 1 Spent Fuel Pool Boron Concentration.................. 3.7.15 1 Spent Fuel AsseFRbly Storage.......................... 3.7.16 1 ELECTRICAL POWER SYSTEMS AC Sources Operating................................. 3.8.1 1 AC Sources Shutdmm.................................. 3. 8. 2 1 Di es el Fuel Oil...................................... 3. 8. 3 1 DC Sources Operating................................. 3.8.4 1 DC Sources Shutdmm.................................. 3. 8. 5 1 Battery Pa raFRete rs................................... 3. 8. 6 1 'l-Inverters Operating.................................. 3.8.7 1 Inverters Shutdmm................................... 3.8.8 1 Di stri buti on SJ'steFRs Operating....................... 3. 8. 9 1 Di stri buti on SJ'steFRs Shutdmm........................ 3. 8.10 1
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REFUELING OPERATIONS 3.9.1 Boron Concentration.................................. 3.9.1 1 3.9.2 Unborated Water Source Isolation Valves.............. 3.9.2 1 3.9.3 Nuclear InstruFRentation.............................. 3.9.3 1 3.9.4 ContainFRent Penetrations............................. 3.9.4 1 3.9.5 Residual Heat ReFRoval CRHR) and Coolant Circulation High Water Level..................... 3.9.5 1 3.9.6 Residual Heat ReFRoval CRHR) and Coolant Ci rcul ati on Lm~ Water Level...................... 3. 9. 6 1
- 3. 9. 7 Refueling Cavity Water Level......................... 3. 9. 7 1
+.-a-DESIGN FEATURES 4-;-+/-
Site................................................. 4. 0 1 44 Reactor Core......................................... 4.0 1 4-;-J Fuel Storage......................................... 4.0 2 BRAIDWOOD UN ITS 1 & 2 AFRendFRent 124
TABLE OF CONTENTS TECHNICAL SPECIFICATIONS
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ADMINISTRATIVE CONTROLS
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Responsi bil i t,y....................................... 5.1 1
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Organization......................................... 5.2 1
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Facility Staff Qualifications........................ 5.3 1
-&A Procedures........................................... 5.4 1
.§-.;...§.
Progr aFRs and ~4anual s................................. 5. 5 1
~
Reporting Requi reFRents............................... 5. 6 1
.fr.+
High Radiation Area.................................. 5. 7 1 BRAIDWOOD UN ITS 1 & 2 AFRendFRent 110
ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.2 Byron Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-37 and NPF-66 Revised Technical Specification Pages i
ii iii iv
TABLE OF CONTENTS TECHNICAL SPECIFICATIONS
-+/---;{}
USE AND APPLICATION
~
Defi ni ti ens.......................................... 1.1 1
~
Logical Connectors................................... 1. 2 1
-+/---: CoFRpl eti on Ti FRes..................................... 1. 3 1
+/-A Frequency............................................ 1. 4 1 b-0 SAFETY LIMITS ( SLs)
~
SLs................................................. 2.0 1 +/-
SL Viol ati ens........................................ 2. 0 1 -;-Q.
LH4ITHJG CONDITIO~J FOR OPERATION ( LCO) MJD SURVEILLANCE REQUIREMENT CSR) APPLICABILITY....................... 3.0 1 -;-}
REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDO't.JN MARG rn ( Srn4)................................ 3.1.1 1 3.1.2 Core Reactivity...................................... 3.1.2 1 3.1. 3
~4oderator TeFRperature Coefficient OffC).............. 3.1. 3 1 3.1. 4 Rod Group Ali gnFRent Li FRi ts........................... 3.1. 4 1 3.1. 5 Shutdmm Bank Insertion LiFRits....................... 3.1. 5 1 3.1.6 Control Bank Insertion LiFRits........................ 3.1.6 1 3.1.7 Rod Position Indication.............................. 3.1.7 1 3.1.8 PHYSICS TESTS Exceptions MODE 2...................... 3.1.8 1 4 POWER DI STRI BUTI mJ LIM ITS 3.2.1 Heat Flux Hot Channel Factor (Ft!(Z))................. 3.2.11
- 3. 2. 2 Nuclear Enthal PJ' Rise Hot Channel Factor CF!+)........ 3. 2. 2 1 3.2.3 AXIAL FLUX DIFFERENCE CAFD)......................... 3.2.3 1 3.2.4 QUADRANT POWER TILT RATIO (QPTR)..................... 3.2.4 1 3.2.5 Departure froFR Nucleate Boiling Ratio CDNBR)......... 3.2.5 1
~
INSTRUMENTATION 3.3.1 Reactor Trip SJ'steFR CRTS) InstruFRentation............ 3.3.1 1
- 3. 3. 2 Engineered Safety Feature Actuation SysteFR (ESFAS) InstruFRentation.......................... 3.3.2 1 3.3.3 Post Accident Monitoring (PAM) InstruFRentation....... 3.3.3 1
- 3. 3. 4 ReFRote Shutdmm SJ'steFR............................... 3. 3. 4 1 3.3.5 Loss of Pml'er CLOP) Diesel Generator CDC) Start I nstruFRentati on.................................. 3. 3. 5 1 3.3.6 ContainFRent Ventilation Isolation InstruFRentation.... 3.3.6 1
- 3. 3. 7 Control RooFR Ventilation (VG) Filtration SJ'steFR Actuation InstruFRentation........................ 3.3.7 1 3.3.8 Fuel Handling Building Exhaust Filter PlenuFR (FHB)
Ventilation SysteFR Actuation InstruFRentation.... 3.3.8 1 3.3.9 Boron Dilution Protection SJ'steFR (BOPS).............. 3.3.9 1 BYRON UNITS 1 & 2 AFRendFRent 116
TABLE OF CONTENTS TECHNICAL SPECIFICATIONS A 3.4.1 3.4.2 3.4.3 3.4.4 3.4.5 3.4.6 3.4.7 3.4.8 3.4.9 3.4.10 3.4.11 3.4.12 3.4.13 3.4.14 3.4.15 3.4.16 3.4.17 3.4.18 3.4.19
~
3.5.1 3.5.2 3.5.3 3.5.4 3.5.5 -; 3. 6. 1 3.6.2 3.6.3 3.6.4 3.6.5 3.6.6 3.6.7 3.6.8
~
3.7.1 3.7.2 3.7.3 3.7.4 3.7.5 3.7.6 REACTOR COOLANT SYSTEM CRCS)
RCS Pressure, TeFRperature, and Fl m,* Departure froFR Nucleate Boiling CDNB) LiFRits............... 3.4.1 1 RCS ~4iniFRUFR TeFRperature for Criticality.............. 3.4.2 1 RCS Pressure and TeFRperature CP/T) LiFRits............ 3.4.3 1 RCS Loops MODES 1 and 2.............................. 3.4.4 1 RCS Loops MODE 3..................................... 3.4.5 1 RCS Loops MODE 4..................................... 3.4.6 1 RCS Loops MODE 5, Loops Filled....................... 3.4.7 1 RCS Loops MODE 5, Loops Not Filled................... 3.4.8 1 Pressurizer.......................................... 3.4. 9 1 Pressurizer Safety Valves............................ 3.4.10 1 Pressurizer Po*vv*er Operated Relief Valves CPORVs)..... 3.4.11 1 Lmv' TeFRperature Overpressure Protection C LTOP)
SJ'steFR........................................... 3. 4.12 1 RCS Ope rational LEAKAGE.............................. 3. 4.13 1 RCS Pressure Isolation Valve CPIV) Leakage........... 3.4.14 1 RCS Leakage Detection InstruFRentati on............... 3.4.15 1 RCS Specific Activity................................ 3.4.16 1 RCS Loop Isolation Valves............................ 3.4.17 1 RCS Loops Isolated................................... 3. 4.18 1 SteaFR Generator CSG) Tube Integrity.................. 3.4.19 1..+-
EMERGENCY CORE COOLING SYSTEMS CECCS)
AccuFRul ators......................................... 3. 5.1 1 EGGS Operating....................................... 3.5.2 1 EGGS Shutdmm........................................ 3.5.3 1 Refueling Water Storage Tank CRWST).................. 3.5.4 1 Seal Injection Flm,*.................................. 3.5.5 1 cmJTAI NME~JT SYSTE~4S Contai nFRent.......................................... 3. 6.1 1 Genta i nFRent Air Locks................................ 3. 6. 2 1 ContainFRent Isolation Valves......................... 3.6.3 1 ContainFRent Pressure................................. 3.6.4 1 ContainFRent Air TeFRperature.......................... 3.6.5 1 Contai nFRent Spray and Cooling SJ*steFRs................ 3. 6. 6 1 Spray Additive SysteFR................................ 3. 6. 7 1 C Deleted)............................................ 3. 6. 8 1 PLANT SYSTrnS Main SteaFR Safety Valves CMSSVs)..................... 3. 7.1 1 Main SteaFR Isolation Valves CMSIVs).................. 3.7.2 1 Secondary Specific Activity.......................... 3. 7. 3 1 SteaFR Generator (SC) Po*vv*er Operated Relief Valves CPORVs)................................... 3.7.4 1 Au><il i ary Feed~.*ater CAF) SJ'steFR...................... 3. 7. 5 1 Condensate Storage Tank C CST)........................ 3. 7. 6 1 BYRON UNITS 1 & 2 AFRendFRent 150
TABLE OF CONTENTS TECHNICAL SPECIFICATIONS
~
3.7.7 3.7.8 3.7.9 3.7.10 3.7.11 3.7.12 3.7.13 3.7.14 3.7.15 3.7.16
~
3.8.1 3.8.2 3.8.3 3.8.4 3.8.5 3.8.6 3.8.7 3.8.8 3.8.9 3.8.10
~
3.9.1 3.9.2 3.9.3 3.9.4 3.9.5 3.9.6 3.9.7
+.-o-4;-+/-
+. 4; PLANT SYSTEMS (continued)
CoFRponent Cool i ng Water CCC) SJ'steFR.................. 3. 7. 7 1 Essential Service Water CSX) SJ'steFR.................. 3. 7. 8 1 UltiFRate Heat Sink CUHS)............................. 3.7.9 1 Control RooFR Ventilation C VG) Filtration SJ'steFR...... 3. 7.10 1 Control RooFR Ventilation CVC) TeFRperature Control SysteFR................................... 3. 7.11 1 Nonaccessible Area Exhaust Filter PlenuFR Ventilation SJ'steFR............................... 3. 7.12 1 Fuel Handling Building Exhaust Filter PlenuFR C FHB) Ventilation SysteFR......................... 3. 7.13 1 Spent Fuel Pool Water Level.......................... 3. 7.14 1 Spent Fuel Pool Boron Concentration.................. 3.7.15 1 Spent Fuel AsseFRbly Storage.......................... 3.7.16 1 ELECTRICAL POWER SYSTEMS AC Sources Operating................................. 3.8.1 1 AC Sources Shutdmm.................................. 3.8.2 1 Di es el Fuel Oil...................................... 3. 8. 3 1 DC Sources Operating................................. 3.8.4 1 DC Sources Shutdmm.................................. 3.8.5 1 Battery Pa raFRete rs................................... 3. 8. 6 1 -j-I nverters Operating.................................. 3.8.7 1 Inverters Shutdmm................................... 3.8.8 1 Di stri buti on SJ'steFRs Operating....................... 3. 8. 9 1 Di stri buti on SJ'steFRs Shutdmm........................ 3. 8.10 1 REFUELING OPERATIONS Boron Concentration.................................. 3. 9.1 1 Unborated Water Source Isolation Valves.............. 3.9.2 1 Nuclear InstruFRentation.............................. 3.9.3 1 ContainFRent Penetrations............................. 3.9.4 1 Residual Heat ReFRoval CRHR) and Coolant Ci rcul ati on High Water Level..................... 3. 9. 5 1 Residual Heat ReFRoval CRHR) and Coolant Ci rcul ati on Lm~ Water Level...................... 3. 9. 6 1 Refueling Cavity Water Level......................... 3. 9. 7 1 DESIGN FEATURES Site................................................. 4.0 1 Reactor Core......................................... 4. 0 1 Fuel Storage......................................... 4. 0 2 BYRON UNITS 1 & 2 AFRendFRent 129
TABLE OF CONTENTS TECHNICAL SPECIFICATIONS
~
ADMINISTRATIVE CONTROLS
~
Responsi bil i t,y....................................... 5.1 1
~
Organization......................................... 5.2 1
~
Facil i t,y Staff Qual ifi ca ti ens........................ 5. 3 1
-&A Procedures........................................... 5.4 1
.§-.;...§.
Progr aFRs and ~4anual s................................. 5. 5 1
~
Reporting Requi reFRents............................... 5. 6 1
.fr.+
High Radiation Area.................................. 5. 7 1 BYRON UNITS 1 & 2 AFRendFRent 116
ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.3 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 Revised Technical Specification Pages i
ii iii iv
TABLE OF CONTEN TS :-+
.;.+;-+/--
~
~ :-l-:-4 +h
~ :-l-:--f. :-l-:-8 :-3
- 3. 3. 1. 1
- 3. 3. 1.2
- 3. 3. 1. 3
- 3. 3. 2. l
- 3. 3. 2. 2
- 3. 3. 3. l
- 3. 3.4. l
- 3. 3. 5. l
- 3. 3. 5. 2
- 3. 3. 5. 3
- 3. 3. 6. l
- 3. 3. 6. 2
- 3. 3. 6. 3
- 3. 3. 7. l
- 3. 3. 7. 2 USE AND APPL ICAT ION Def i ni t i ons.............................................. 1. 1 1 Logi ca l Connectors....................................... 1. 2 1 Comp l etion Ti mes......................................... 1. 3 1 Frequency................................................ 1. 4 1 SAFETY LIMI TS (SLsl SLs...................................................... 2. 0 1 SL Vio l ations............................................ 2.0 1 LIMITI NG CO NDITION FOR OPERATION (LCO) APPLICABILITY........ 3.0 1 SURVE I LLA NCE REQU I REME NT (SR) APPL ICABI LITY................. 3.0 4 REACT IVITY CO NTROL SYSTEMS SHUTDOIHJ MARG HJ ( smn.................................... 3. 1. 1 1 Reactiv i ty Anoma l ies..................................... 3. 1. 2 1 Contro l Rod OPERABIL ITY.................................. 3. 1. 3 1 Contro l Rod Scram Ti mes.................................. 3. 1. 4 1 Contro l Rod Scram Accumulators........................... 3. 1. 5 1 Rod Pattern Contro l...................................... 3.1. 6 1 Standby Liquid Contro l (SLC) System...................... 3. 1. 7 1 Scram Di sc harge Vo l ume (SDV) Vent and Drain Valves....... 3. 1.8 1 POWER DISTR IB UT ION LIMITS AVERAGE PLMJAR LHJEAR HEAT GE ~JERATIO ~J RATE (APLHGR)...... 3. 2. l 1 MINI MUM CR ITICAL POWER RAT IO (MCPR)...................... 3. 2. 2 1 LI NEAR HEAT GE NERATIO N RATE (LHGR)...................... 3. 2. 3 1 I ~J STRU~4 E
~JTATI 0 ~J Reactor Protect i on System (RPS) Instrumentation.......... 3. 3. 1. l 1 Source Range Mon i tor (SRM) Instrumentat i on............... 3. 3. 1. 2 1 Osc ill ation Power Range Mon i tor (OPRM) Instrumentation... 3. 3. 1. 3 1 Contro l Rod Bl ock Instrumentation........................ 3. 3. 2. l 1 Feedwater System and Ma i n Turb i ne Hi gh Water Level Tr i p Instrumentat i on................................... 3. 3. 2. 2 1 Post Accident Mon i tor i ng (PAM) Instrumentation........... 3. 3. 3. l 1 Anticipated Transient Without Scram Recirculation Pump Tr i p (ATWS RPT) Instrumentat i on................... 3. 3.4. l 1 Emergency Core Cooli ng System (EGGS) Instrumentation..... 3. 3. 5. l 1 Reactor Pressure Vesse l ( RPV) \\Jater Inventory Contro l
+
Instrumentation....................................... 3. 3. 5. 2 1 Iso l at i on Con denser (IC) System Instrumentation.......... 3. 3. 5. 3 1 Pr imary Conta i nment Iso l at i on Instrumentation............ 3. 3. 6. l 1 Secondary Conta i nment Iso l ation Instrumentation.......... 3. 3. 6. 2 1 Re l ief Va l ve Instrumentation............................. 3. 3. 6. 3 1 Contro l Room Emergency Vent il at i on (GREV) System Instrumentation....................................... 3. 3. 7. l 1 Mechan i ca l Vacuum Pump Tr i p Instrumentation.............. 3. 3. 7. 2 1 (cont i nued)
Dres den 2 an d 3
+
Amen dment No. 256/249
TA BLE OF CONTEN TS : 3. 3. 8. l 3.3.8.2 :-4 :-+.-}
~ :-4-:-3 :-4-:-4
~
~ :-4-:--f. :-4-:-8
~
3.4. 10 :- 3. 6. l. 1 3.6. 1. 2 3.6. 1. 3 3.6. 1. 4 3.6. 1. 5 3.6. 1. 6 3.6. 1. 7 3.6. 1. 8 3.6.2. 1 3.6.2.2 3.6.2.3 3.6.2.4 3.6.2. 5 3.6.3. 1 3.6.4. 1 3.6.4.2 3.6.4.3 IN STRUM EN TAT ION,
L (continued) oss of Power (LOP Reactor Protect *
) Instrumentation.
i on S:yst
(
Safety ae~ - R~ i i~f *;,- i ************** ::: ******************- 3. 4.l 1 CS Oeeratieea l LE ; K. ~E................................ 3. 4. 2 1 R
M 3 4 ea ka§e Deteet.
- * * * * * * * *. 3 1 RCS Seeeifie *et *7':' lestr,meetatiee
- ** ** ** ** ** ** **. 3. 4. 4 I M
i Ji -y' SA,trle*,1e Ceeli A§ (SD - * * * * * * * * *..........
....... * * * * * * *
- 3. 4. 5 I SA,t rlewe Ceeli A§ (SD~: S~stem Het SA,trle~~:: :: : *.. ** ** **. 3. 4. 6 I RCS Press "'e aerl T S; stem Ge l rl SA,trle"A
- * * * * * * * *. 3. 4. 7 I Reaeter Steam Dem e:eerat,re IP/Tl Limits".............. 3. 4. 8 I e
res sure 3 4 g 1 EMERGE NCY CORE COO LIN G
....................... **. : :: :3:4:10 1 WATER INVE NTORY CO NTR SY~TE M S (EGGS), REACTOR p 1c's;stem eveetery Ceetre l.. :::::: **********************
3. 5. l I CO NTA IN ME NT ~~~~ ;~~................... : : : : : : : : : : : : : : : : : : : : : : ~: ; : ~ : +
Pr~mary Containment Pr i mary Conta i nment *~ ~....................
Pr i mary Ceeta i emeet" ' Leek.............. ::............. 3. 6. 1. 1 I Dry11ell Press,re lse l at i ee Valves IPC ! Vsl............. 3. 6. 1. 2 I Dry11ell Ai, Teme~;;t.. * * * * * * *............... : * * * * * * * * * * *
- 3. 6. I. 3 1 Le" s t
"'e
- 3 6 1 4 vvC Re l i cf "al " CS 1
R 3 6 eaeter B" il di A§ te S;~ ~ ; ***:*****************.......... -. -. 1. 5 I BreakePS
---essiee CAamBer "
- * * * * * * * * *. 3. 6. 1. 6 1 s
vacuum u1313ressi on Chamb~~
- t *
- B * * * * * * * *...........
S e - ry* *ell "
3 6 "eeress i ee Pee l...
wae""m BreakePS
- * * * * * * *. -. -. 1. 7 I s,eeress i ee Pee l ~*:Fa§e Temeerat,,e....
... * * * * * * *. 3. 6. 1. 8 I s
.. a er Le "el 3
"eeressiee Pee l Gee l.
- * * * * * * * * *. 6. 2. l I s,eeressiee Pee l S lA§. * * * * * *.................. * * * * * *. 3. 6. 2. 2 I 8
- nra ~
ry11ell t S
........ * * * * *
- 3
- 6. 2 3 I p.
e "eeress i ee CA 0 r i mary Ceeta i emeet 0 : - am-er Di ffereet i al p,~ * ** ** ** **. 3. 6. 2. 4 I Seeeerlary Ceet.
- §eA Ceeeeetratiee ss,re.. **. 3. 6. 2. 5 1 S
ainment eeeerlary Ceetai
- ** ** ** **. 3. 6. 3 1 1 St d
emeet lse l at
- 3 6 an by Gas Trea t men t rs ion Va l ves (SC IVs)............ 4. 1 1
( GT) System....
- * * * * * * * * *.3.6.4.2 1
................... 3.6.4.3 1 (continued) 8res den 2 an d 3 Amen dment No. 256/249
TABLE OF CONTEN TS (con t inued)
~
'3-:-t-:-+/-- :-7--: -3-:-7--:-3 :-t-:-4 :-f-:-5. :-B :-B-:-+/--
~
~
~ :-8-: ~ :-8-;-f.
~ :4 ;-9-;-+/--
~ :-9-:-3 :-9-:-4
~
~
~
- 3. 10. l
- 3. 10. 2
- 3. 10. 3
- 3. 10.4
- 3. 10. 5
- 3. 10. 6
- 3. 10. 7
- 3. 10.8 PLA NT SYSTEMS Conta i nment Cooli ng Serv i ce 'tlater (CCSIJ) System.......... 3. 7. 1 1 Di ese l Generator Coo l in g Water (DGCW) System............. 3. 7. 2 1 Ul timate Heat Sink (UHS)................................. 3. 7. 3 1 Contro l Room Emergency Vent il at i on (GREV) System......... 3. 7.4 1 Contro l Room Emergency Vent i lat i on Air Con dit i on i ng (AC) System............................... 3. 7. 5 1 Main Condenser Off gas.................................... 3. 7. 6 1 Main Turbine Bypass System............................... 3. 7. 7 1 S p e n t F u e l S t o r a g e P o o l \\J a t e r Le v e l...................... 3. 7. 8 1 ELECTR ICAL POW ER SYST EMS AC Sources Operating..................................... 3.8. l 1 AC Sources Shutdo*,m...................................... 3. 8. 2 1 Di ese l Fue l Oil and Start i ng Ai r......................... 3.8. 3 1 DC Sources Operat i ng..................................... 3.8.4 1 DC Sources Shutdo*,m...................................... 3. 8. 5 1 Battery Parameters....................................... 3.8. 6 1 Di str i but i on Systems Operat i ng........................... 3.8. 7 1 Di str i but i on Systems Shutdown............................ 3.8.8 1 REFUEL IN G OPERAT IONS Refue li ng Equ i pment Inter l ocks........................... 3. 9. l 1 Refue l Pos i t i on One Rod Out Inter l ock.................... 3. 9. 2 1 Contro l Rod Position..................................... 3. 9. 3 1 Con t ro l Rod Pos iti on Indi ca ti on.......................... 3. 9.4 1 Contro l Rod OPERA BI LITY Refue li ng........................ 3. 9. 5 1 Reactor Pressure Vesse l (RPV) Water Leve l Irradiated Fue l.................................. 3. 9. 6 1 Reac t or Pressure Vesse l (RPV) Water Level New Fue l or Contro l Rods................................... 3. 9. 7 1 Shutdown Cooli ng (SDC) Hi gh Water Leve l.................. 3. 9.8 1 Shutdown Coo l ing (SDC) Low Water Leve l................... 3. 9. 9 1 SP ECIAL OP ERAT IONS Reactor Mode Swi tc h Inter l ock Test i ng.................... 3. 10. l 1 Si n g l e Cont r o l Rod ',.'i t h d r a *vr a l Hot Sh u t do ~m............... 3. 10. 2 1 Si n g l e Contro l Rod l.'i th d r a *vra l Co l d Shut d o*,m.............. 3. 10. 3 1 Si ng l e Contro l Rod Dr i ve (CRD)
Remova l Refue li ng...................................... 3. 10. 4 1 Mu l ti pl e Contro l Rod \\.'i th d r m1a l Refue l i n g................ 3. 10. 5 1 Con t ro l Rod Tes ti ng Opera ti ng............................ 3. 10. 6 1 SHUTDOW N MARG IN (SDM) Tes t Refue li ng..................... 3. 10. 7 1 Inserv i ce Leak and Hydrostat i c Test i ng Operation......... 3. 10.8 1 (cont i nued)
Dres den 2 an d 3 Amen dmen t No. 248 / 241
+
TABLE OF CO NTE NTS
( continued)
~
DES I GN FEATURES 4-:-+/-
Si te Locat i on............................................ 4. 0 1
~
Reactor Core............................................. 4. 0 1 4-:-3 Fu el Sto r age............................................. 4. 0 2
~
ADMI NISTRATIVE CO NTROLS : Respons i bi li t y........................................... 5. 1 1 : Or ganization............................................. 5. 2 1 : Unit Staff Qua l ifi cations................................ 5. 3 1 :-4 Procedures............................................... 5. 4 1 : Programs and Manua l s..................................... 5. 5 1 : Repo r t i ng Requ i rements................................... 5. 6 1 : High Radiati on Ar ea...................................... 5. 7 1 Dresden 2 and 3 Amendment No. 248 / 241
ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.4 James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 Revised Technical Specification Pages i
ii iii iv
TAElbE OFi CONTENTS 4--0 USE AfliJD APPLICATIOfliJ 44 Definitions............................................................................................ 1.1 1
~
Logical Connectors.............................................................................. 1.2 1
~
Completion Times................................................................................ 1.3 1 44 F"requency............................................................................................ 1.4 1
~
SAF"ETY LIMITS (SLs)
M SLs..................................................................................................... 2.0 1
~
SL Violations........................................................................................ 2.0 1
&.-0 LIMITlfliJG COfliJDITIOfliJ F"OR OPERATIOfliJ (LCO) APPLICABILITY........... 3.0 1
&.-0 SURVEILLAfliJCE REQUIREMEfliff (SR) APPLICABILITY.......................... 3.0 3 a-4 REACTIVITY COfliffROL SYSTEMS
~
S"1UTDOVVfliJ MARGlfliJ (SOM)............................................................. 3.1.1 1
~
Reactivity Anomalies........................................................................... 3.1.2 1
~
Control Rod OPERABILITY................................................................. 3.1.3 1
~
Control Rod Scram Times................................................................... 3.1.4 1 a..,..+.,.a Control Rod Scram Accumulators....................................................... 3.1.5 1
~
Rod Pattern Control............................................................................. 3.1.l 1
~
Standby Liquid Control (SLC) System................................................. 3.1.7 1
~
Scram Discharge Volume (SDV) Vent and Drain Valves.................... 3.1.8 1
~
POVVER DISTRIBUTIOfliJ LIMITS
~
AVERAGE PLAfliJAR LlfliJEAR "1EAT GEfliJERATIOfliJ RATE (APL"1GR)3.2.1 1
~
MlfliJIMUM CRITICAL PO'.A/ER RATIO (MCPR)................................... 3.2.2 1
~
LlfliJEAR "1EAT GENERATIOfliJ RATE (L"1GR).................................... 3.2.3 1
~
3.3.1.1 3.3.1.2 3.3.2.1 3.3.2.2 3.3.3.1 3.3.3.2 3.3.4.1 3.3.5.1 3.3.5.2 3.3.5.3 3.3.0.1 3.3.0.2 3.3.7.1 3.3.7.2 3.3.7.3 JAF"fliJPP lfliJSTRUMEfliffATIOfliJ Reactor Protection System (RPS) Instrumentation............................. 3.3.1.1 1 Source Range Monitor (SRM) Instrumentation................................... 3.3.1.2 1 Control Rod Blocl'\\ Instrumentation...................................................... 3.3.2.1 1 F"eed'.vater and Main Turbine "1igh 'Nater Level Trip Instrumentation..................................................................... 3.3.2.2 1 Post Accident Monitoring (PAM) Instrumentation................................ 3.3.3.1 1 Remote Shutdovm System.................................................................. 3.3.3.2 1 Anticipated Transient VVithout Scram Recirculation Pump Trip (ATVVS RPT) Instrumentation.................................... 3.3.4.1 1 Emergency Core Cooling System (EGGS) Instrumentation................ 3.3.5.1 1 Reactor Pressure Vessel (RPV) \\Nater Inventory Control Instrumentation................................................................ 3.3.5.2 1 Reactor Core Isolation Cooling (RCIC) System Instrumentation............................................................................ 3.3.5.3 1 Primary Containment Isolation Instrumentation................................... 3.3.l.1 1 Secondary Containment Isolation Instrumentation.............................. 3.3.l.2 1 Control Room Emergency Ventilation Air Supply (CREVAS)
System Instrumentation............................................................... 3.3.7.1 1 Condenser Air Removal Pump Isolation Instrumentation.................... 3.3.7.2 1 Emergency Service 'Nater (ESW) System Instrumentation................. 3.3.7.3 1 Amendment 321 t
+
TABLE: Of GONTE:NTS
~
3.3.8.1 3.3.8.2 J4 M4
~
~
M-4
~
~
a.4:-7 u
3.6.1.1 3.6.1.2 3.6.1.3 3.6.1.4 3.6.1.5 3.6.1.6 3.6.1.7 3.6.1.8 3.6.1.9 3.6.2.1 3.6.2.2 3.6.2.3 3.6.2.4 3.6.3.1 3.6.3.2 3.6.4.1 3.6.4.2 3.6.4.3 l ~JSTRUME~JT A T I O~J (
L continued) oss of Power (LOP)
Reactor ProtecUon s;:t~t:m~ntation...................
MeAileriAg
( PS) Elestris Power...................... d.d.8.1 1 REACTOR COOLAN*; *~;~;............................................................... d.d.8.2 1 Recirculation Loops 0 EM_ (RCS) d t p perat1ng eumps sa1e1y1Re1 ;cl y~1~~ <es (PGii;"")............................ d.S 1 2 1 ffr ressure 4
vS......
g d61d1 rywell
- ir T n
emperature 3
Reaster B"i18iAg le S
.................. -.S.1.4 1 S"ppressieA CRa 8 "ppressieA CRamBe~ V~~~~;;;i.... i.......... d.S.1.5 1
, 4.
m er le gpouell, 1 rea <ers a s 16 r alA Steam Leal' H
, as""m Breal<e
... 1 Resi8"al '"eat R <ag~, CellestieA (M SLC) System rs.................. d. S.1. + 1 s
eme. al (RflR) c t
- d S 1 8 1 "ppressieA Peel Averag ;
e" mAmeAI Spray Syst~;;; * * -- * -- ;;*.
- S"ppressieA Peel ' t e emperat.re..........
. S.1.Q 1 R
" a er Le><el d S 2 1 esi8"al '"eat Rem I (
............ -... 1 grywell te s"ppres;: c~'"R) S"ppressi~~ *p~~i *G~~ii~~ * *-- -- * -- d.62.2 1 Primary CeAlaiAmeAI 0, amBer g11fereAlial Press"re
......... d.S.2.d 1 CeAlaiAmeAI Alm
- ygeA CeAseAlralieA........
.............. d.S.24 1 SeseA8ary CeAla~spRere g 11"t1eA (CAg) System...................... d.S.d.1 1 S
AmeAI d S d 2 eseA8ary Ce RIO
.. *.. *.... * * -. *. 1 SlaA8By Gas Tre i~meAI lselalieA Va lv~~ (SG iii~)................. d.S.4.1 1 a ment (SGT) System
...................... 3.6.4.2 1
'"eat SiAI< (U'"S)
(ES ~) System aA8 Ultimate
......... d.7.1 1
.................................................................. 3.7.2 1 Amendment 321
-t---
J-.-7
~
d-:-7-: ~
~
~
~
~
~
~
~
~
3.s.-6
~
~
3-:-9
~
~
~
3-:-9-:4 3-:-9-;-§ d-:--9-:-6 3-:--9-:-7
~
3-:--+/-e 3.10.1 3.10.2 3.10.3 3.10.4 3.10.5 3.10.6 3.10.7 3.10.8 4-:-9 H
4-:-2 4-:-3 JAFNPP PLANT SYSTEMS (CORtiRYed)
GoRtrol ROORI ERlergeRcy VeRti l ati OR Air Syppl y ( GRE'/.~ )
SysteRI GoRtrol ROORI Air GoRditioRiRQ (AG) SystCRI....
MaiR GoRdeRser SteaRI Jet Air Ejector CSJAE) Offgas MaiR TYrbiRe 8ypass SysteRI.....
SpeRt F"Yel Storage Pool Water Level.......
ELECTRICAL POWER SYSTEMS
~~ ~g~:~g~ ~~~~:!:§. : : : : : : : : : : :
Diesel F"uel Oil, Lube Oil, and Starting Air DC Sources Operating
~
DC Sources Shutdown......
Battery Gell ParaRleters 7 ***
~~;i:~g~i~:: ~~~ig:; ~c~~~~=g
- REFUELING OPERATIONS RefueliRg EquipmeRt IRterlocks Refuel Position 0Re Rod Out IRterlock Control Rod PositioR.........
CoRtrol Rod PositioR IRdicatioR -. -.-.
CoRtrol Rod OPERABILITY Refueling...
Reactor Pressure \\'essel CRP\\') Water Level Residual Heat Removal CRHR)
High Water Level Residual Heat Removal CRHR)
Low Water Level.
SPECIAL OPERATIONS IAservice Leak aAd Hydrostatic TestiAg OperatioA Reactor Mode Switch IAterlock TestiAg.....
SiAgle CoAtrol Rod Withdrawal Hot Shutdown ~
SiAgle CoAtrol Rod Withdrawal Cold Shutdown..
SiAgle CoAtrol Rod Dri*ve CCRD) Removal RefueliAg Multiple Control Rod Withdrawal Refueling CoAtrol Rod Testing Operating....
SHUTDOWN MARGIN CSDM) Test RefueliAg......
DESIGN FEATURES Site LocatioA Reactor Core.
Fuel Storage.
3.7.J 1 J.7.4 1 J.7.9 1 J.7.e 1 J.7.7 1 J.8.1 1 3.8.2 1 3.8.3 1 3.8.4 1 3.8.9 1 3.8.e 1 3.8.7 1 3.8.8 1 3.9.1 1 3.9.2 1 3.9.3 1 3.9.4 1 3.9.5 1 3.9.6 1 3.9.7 1 3.9.8 1 3.10.1 1 3.10.2 1 3.10.3 1 3.10.4 1 3.10.5 1 3.10.6 1 3.10.7 1 3.10.8 1 4-:H 4-:H 4.0 2 (continued)
Amendment 274
TABLE OF CONTENTS Ceontinued) 5-:-t}
ADMINISTRATIVE CONTROLS 5-:"f Responsibility...
5-:-Z Orga1ii zati on....
5:-3 Plant Staff Qualifieat ions 5-:-4 P1oeedo1es......
5-:-5 Programs and Manuals.
5-:-'6 Reporting Requirements H
llign Radiat ion Area JAFNPP iv Ame11dment 274
ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.5 R.E Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18 Revised Technical Specification Pages LCO-i LCO-ii LCO-iii LCO - iv
TABLE OF CONTENTS
.:kG USE ANO APPLICATION U
Definitions......................................................................................................... 1.1 1
~
Logical Connectors.................................................................................. 1.2 1
.+,3 Completion Times................................................................................... 1.3 1,.4 Frequency....................................................................................................... 1.4 1
~
SAFETY LIMITS (SLs) 2-,4.
SLs................................................................................................................... 2.0 1
~
SL \\tiolations............................................................................................ 2.0 1 l,.Q LIMITING CONDITION FOR OPERA.TION (LCO) ANO SURVEILLANCE REQUIREMENT (SR) APPLICABILITY l,.Q Limiting Condition for Operation (LCO) Applicability........................... 3.0 1 J.,.G.
Surveillance Requirement (SR) Applicability...................................... 3.0 4
~
REACTIVITY CONTROL SYSTEMS
~
SHUTOOVVN MARGIN (SOM)......................................................................... 3.1.1 1 3..-+.2 Core Reactivity................................................................................................. 3.1.2 1
~
Moderator Temperature Coefficient (MTC)............................................... 3.1.3 1 J.A-4 Rod Group Alignment Limits.................................................................... 3.1.4 1 3..-+.5 Shutdown Bank Insertion Limit................................................................. 3.1.5 1
~
Control Bank Insertion Limits................................................................... 3.1.6 1
~
Rod Position Indication............................................................................ 3.1.7 1
~
PHYSICS TESTS Exceptions MOOE 2.................................................. 3.1.8 1
~
POWER DISTRIBUTION LIMITS
~
Heat Flux Hot Channel Factor (Fa(Z))...................................................... 3.2.1 1
~
Nuclear Enthalpy Rise Hot Channel Factor (Ft:!.L:.11)................................... 3.2.2 1
~
AXIAL FLUX DIFFERENCE (AFO)........................................................... 3.2.3 1
~
QUADRANT POVVER TILT RATIO (QPTR)............................................. 3.2.4 1
~
INSTRUMENTATION
~
Reactor Trip System (RTS) Instrumentation............................................. 3.3.1 1
~
Engineered Safety Feature Actuation System (ESFAS) Instrumentation.. 3.3.2 1
~
Post Accident Monitoring (PAM) Instrumentation..................................... 3.3.3 1 3-,M Loss of Power (LOP) Diesel Generator (OG) Start Instrumentation.......... 3.3.4 1
~
Containment Ventilation Isolation Instrumentation..................................... 3.3.5 1
~
Control Room Emergency Air Treatment System (CREA.TS) Instrumentation Actuation.............................................. 3.3.6 1 R. E. Ginna Nuclear Power Plant LCO Amendment 100
~
~
~
MA
~
~
~
~
~
M-A-Q
~
~
~
~
~
~
~
~
~
~
~
3.-5.4
~
~
~
~
~
~
~
+-
LCO ii
3-.a 3-.a.+
~
~
3-.M
~
~
3-.a.+
~
~
~
TABLE OF CONTENTS PLANT SYSTEMS (continued)
Condensate Storage Tanks (CSTs)
Component Cooling 'Nater (CCVV) s-~~t *************************************************** 3.7.6 1 Service Water (SI/I/) System Y em ***************************************
....... 3.7.7 1 Control Room Emergency A.i-~"T~~~t,:;;~~*t ************* ************************************ 3.7.8 1 System (GREATS)............
Auxiliary Building Ventilation Syste~ * (*~*s \\~*si)........................................... 3.7.9 1 Spent Fuel Pool (SFP) 'Nater Level "
Ir
...................................................................... 3.7.14 1 ELECTRICAL POWER SYSTEMS AC Sources MODES 1, 2, 3, and 4 AC Sources MODES 5 and 6 3.8.1 1 Diesel Fuel Oil
- * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *... 3.8.2 1 DC Sources MOD°Es**1**2"*3******d**********************************************************
3.8.3 1 DC Sources MODES 5 ' a~d 6 an 4....................................................... 3.8.4 1 Battery Cell Parameters
- * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *. 3.8.5 1
~~ :n*:rYment Bys Soy;;;~~00MQDES 1: 2: J: ~~d 4
- g
"~
~s rument Bus Sources MODES 5 and 6 Distribution Systems MODES 1 2 3
- * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *... 3.8.8 1 Distribution Systems MODES 5 ~nd 6 and 4 * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *... 3.8.9 1
.................................................... 3.8.101 REFUELING OPERATIONS Boron Concentration Nuclear lnstrumentati~~ **************************** ------------------------------------------------------* 3.9.1 1 Containment Penetratio~~ ****************************----.............................................. 3.9.2 1 Residual Heat Removal (RHR) *~~~i *c~~i~~t............................................ 3.9.3 1 Circulation Water Level ~ 23 Ft Residual Heat Removal (RHR) and Co~i~~*t ******************************************** 3.9.4 1 Circulation Water Level < 23 Ft Refueling Cavity 'Nater Level
- * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *. 3.9.5 1
................................................................... 3.9.6 1 DESIGN FEATURES Site Location Reactor Core*********************************************************************************
.......... 4.1 1 Fuel Storage::::::::::::::*****************************************************************************
4.2 1
............................................................................. 4.3 1 ADMINISTRATIVE CONTROLS Responsibility....................................
Organization
.............................................................. 5.1 1 Plant Staff Q~~-1iii~~ii~~~ * * * * * * * * * * * *.................................................................... 5.2 1 P
5 3 1 rocedures.
..................................................................................................... 5.4 1 R. E. Ginna Nuclear Power Plant LCO iii Amendment 100
TABLE OF CONTENTS Programs and Manuals..................................................................... 5.5 1 Reporting Requirements................................................................... 5.6 1 High Radiation Area......................................................................... 5.7 1 R. E. Ginna Nuclear Power Plant LCO iv Amendment 100
ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.6 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 Revised Technical Specification Pages i
ii iii iv
TABLE OF CONTEN TS ;-} :-l--: ~
~ :-+.-4 :-l--: -3-:-l--: -3-+: -3-:-+.-8 :-3
- 3. 3. 1. 1
- 3. 3. 1. 2
- 3. 3. 1. 3
- 3. 3. 2. l
- 3. 3. 2. 2
- 3. 3. 3. l
- 3. 3. 3. 2
- 3. 3.4. l
- 3. 3.4. 2
- 3. 3. 5. l
- 3. 3. 5. 2
- 3. 3. 5. 3
- 3. 3. 6. l
......... 1. 1 1 USE AND APPLICATI ON
....... 1. 2 1 1. 3 1 Defi ni t1 ens........
Lo§1 ea l coeeeeto PS * * * *
........ * * * * * * * * * * * * * *
- 1. 4 1 Complet i on T1 mes.......
Frequency * * * * * * * * * * * * * * * * * *
.......... 2. 0 1 SAFETY LI MITS (SLsl
......................... : :.......... 2. 0 1 S Ls.. * * * * * * * *.......
SL " i ol at i oAS...........
y 3. 0 1 PER ' TION (LCOI APPLICA BILIT..... :: :3. 0 4 LIMITI NG CONDITION FOR N ~ (S~l APPL ICAB ILITY..............
SURVE I LLA NCE REQUI REME
- 3. 1. 1 1
" !TY CONTROL SYSTEMS
........................ : : : : 3. 1. 2 I REn~:~;DOWN MARCIN ISDMI....... :....................... *.... 3. 1. 3 I Rea:t i ; i ~~/8~:~A: ~:j TY : : : : * * * * * : : : : : : : : : : : : : : : : : : : : * * * ~::: i :
GOA "
m Ti mes... *******
COAtPO l Ro<l Sepa
' cc,., l atoPS............
....... 3. 1. 6 :
CoetPo l Ro<l Sepam n
. 3. 1. I Ro a Pattm c""~"~;~ i
- (SLG i
- S;stem...... : ; *;, ;i~~;::::::
. 3. 1. B I Standby Li qu i d
~ n (SDV) Vent and Dra1 Dl' sc harge vol ume Scram HHTS
(' PLHGR)...... 3.2. l l PO"ER DI STR I BUTION L
- ;; HE' T GE NERATION RATE ** --- -
.... 3. 2. 2 I
", " ERACE PLA NAR LI NEn R R:TIO IMCPRI..................... 3. 2. 3 I RV C' L PO" E-R MINI MUM CR ITI n R:TiON RATE (LHGR)..............
LI NEAR HEAT GENE n
- 3. 3. 1. 1 1 ON t
meetatioe. ** ** ** **
- 3 1 2 I I NSTRUME NTATI
. A System IRPSI l es - r'- : -,
............. 3.. -.
Reactor Protect1otoP ESRMI lestP,meetat;o i;,meetatioe... 3. 3. 1.3:
So,Pee Rae§e Moe1 Moe i tor IOPRMI AS
........ 3. 3. 2. I
- 11 at i on Power Range t t i on.. **************
~::: Po l Ro<l Bl ock Iestr,me;::;iee Hi§A WateP Le vel 3. 3. 2. 2 I Fee<lwateP System ae<l Maia
............. *:.......... :: :3. 3. 3. l I Tri~ I est.,meeta t1 oe... (PAM I I est,,meetat10e.... : : : :... 3. 3. 3. 2 I t ' cc i den t
~1 on 1 term ?
S 'Stem................
~:!;t; SA,t<lo11e MOA i ~o ; ; :: P:m~ T;i ~ 1 EOG RPT I
......... 3. 3. 4. 1 I E d of Cyc l e Rec1rcu a A
, 1at1oe 2 1 I est "meetat10e :.. i ", 'i Ho't Se pam Reei Pe
...... 3. 3. 4.
d TraASlEA 3 5 1 I AA t i Ci ~ate - ; :~~.~ RPT I I ASt,,meeta t; o~. ;i;;~eetati BA..... 3. -. -.
p,_~ Tri~ " "
. A System I EGGS A
Control
~
EmeP§EAey COPE Co~ll § l I RPV I II ate' I 8'eAtOPy
......... 3. 3. 5. 2 1 Reactor Pressu~e vesse........................
Iestr,meetat1oe. *:... Gooli a§ ERCICI System
... 3. 3. 5. 3 1 ReaetOP COPE lsolat10A
... 3.3.6.1-1 Instrumentat i on..... ' i ~tion Instrumentat ion.......
PPimaPy Coetaiemeet !so (eoet i e,e<ll LaSa ll e 1 an d 2
+
230/2 16 Amen dmen t No,
TABLE OF CONTEN TS : 3. 3. 6. 2
- 3. 3. 7. 1
- 3. 3.8. 1
- 3. 3.8. 2 : -3-:-4-: ~
~ :-4-:-4 :-4-: ~
3.4.7 3.4.8 3.4.9 3.4. 10 3. 4. 11 3.4. 12
~
- 3. 5. 2
- 3. 5. 3
- 3. 6
- 3. 6. 1. 1
- 3. 6. 1. 2
- 3. 6. 1.3
- 3. 6. 1. 4
- 3. 6. 1. 5
- 3. 6. 1. 6
- 3. 6. 2. 1
- 3. 6. 2. 2
- 3. 6. 2. 3
- 3. 6. 2.4
- 3. 6. 3. 1
- 3. 6. 3. 2
- 3. 6.4. 1
- 3. 6.4. 2
- 3. 6.4. 3 IN STRU MEN TAT ION (cont i nued) 3 3 6 2 1 Secondary Conta i nment Iso l at i on Instrumentation..... ***** * *
- Contro l Room Area Fil tration (GRAF) System 3 3. 7. 1 1 Instrumentation.**************:************************
3
- 3 8 1 1 Loss of Power (LOP) Instrumentation... :.*****************
Reactor Protect i on System (RPS) Electric Power
..... 3. 3.8. 2 1 Monitorin g................. ***********************
3.4. 1 1 Rec i rcu l at i on Loops Operat i ng.**************************
0 3 4 2 1 l
(FC"sl Fl ow Contro l Va ves v
3.4. 3 1 Jet Pumps................................................ 3 4 4 1
. f
\\I l
( s IR" s )
Safety / Re l i e va ves
, v..............
- 3 4 5 1 RCS Operat i ona l LEAKAGE.................................. 3.4*6-l RCS Pressure Iso l at i on Va lv e (PIVl. Leaka ge............... 3.4. 7 1 RCS Leakage Detect i on Instrumentat i on................... :3:4:8-1 RCS Specific Activity........ * * * * * * * * * * * * : * * * * * * * * * * * * *
- Re sid ua l Hea t Remova l (RHR) SAutdo*,m Coolrn g
. 3.4. 9 1 ts "' td **n System Honu On........ * * * * * * * * *
- Res i dua l Heat Remova l (RHR) SAutdo*,m Coolrng
...... 3.4. 10 1 System Co l d SAutdown. * * * * * * * * * * * * *: *: * * * * * * * * * * *
- 3 4 11 1 RCS Pressure an d Tempera t ure (P/Tl Li mi ts............... *3*4 : 12 1 Reactor Steam Dome Pressure........ **********************
~~~~~E~~~E~~~~yc~~~~~~L ~ y!!~M~E!g~~)c o ~~A~~~:A;~6~s~~6Li ~ ~s~~ci~~V) 1-SYSTEM 3 5. 1 1 EGGS Operat i ng.*******************
...................... *3: 5. 2 1 +
RPV water Inventory Contro l *****************************
- 3. 5.3 1 RC IC Sys t em............ **********************************
CO NTA INMENT SYST EMS
... 3. 6. 1. 1 1 Primary Containment.. *********************************
3 6 1. 2 1 Pr imary Con t ai nment Ai r Lock.****************************
' 6 ' 1 3 1 Pr imary Conta i nment Iso l at i on Va l ves (PCIVs). * * * * * * * * * * *.3. * *4 1 Drywell and Suppress i on CAamber Pressure.***************
- 3
- ~
- 5 1 t
........... 3...
Drywell Air Tempera ure. * * * * * * * * * * * * * * * * * * * * *
- 3 6 1 6 1 CAamber t o Dr)"vre l l Vacuum Breakers... ******** * *
- 1 Suppress i on 3 6 2 2 1 s u r e s s i o n P o o l \\J a t e r Le v e l.. * * * * * * * * * * * * * * * * * * * : * * * * * * * * *
- 3 R p~d al Heat Remo"al (RHR) Suppression Poo l Cool m g... *. 3. 6. 2.
1 Res:/a 1 Hea t Remo: al (RHR) Suppression Poo l Spray.*****. 3. 6. 2.4 1 es i U v
3 6 3 1 1 Pr imary Conta i nment Hydrogen Recombin?rs................ *3*6*3*2 1 Pr imary Conta i nment Oxygen Concentrat i on................ *2*6 *4*1 1 Seconda ry Genta i nment. * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- 3 6 4 2 1 Secondary Con t ai nmen t Iso l ati on Va l ves (SC IVs).......... *3*6:4:3 1 Standby Gas Treatment (SGT) System.... *******************
(con ti nued)
LaSa ll e 1 an d 2 Amen dmen t No. 230/2 16
TA BLE OF CON TEN TS (con t inue d)
~
'3-:-t-:-+/-- :-7--: -3-:-7--:-3 :-t-:-4 :-f-:-5. :-B :-B-:-+/--
~
~
~ :-8-: ~ :-8-;-f.
~ :4 ;-9-;-+/--
~ :-9-:-3 :-9-:-4
~
~
~
- 3. 10. l
- 3. 10. 2
- 3. 10. 3
- 3. 10.4
- 3. 10. 5
- 3. 10. 6
- 3. 10. 7
- 3. 10.8 PLA NT SYSTEMS Res id ua l Heat Removal Serv i ce 'tJater (RHRSIJ) System....... 3. 7. 1 1 Di es el Generator Coo l in g 'tJater ( DGC IJ ) System............. 3. 7. 2 1 Ul timate Heat Sink (UHS)................................. 3. 7. 3 1 Contro l Room Area Fi ltration (GRAF) System............... 3. 7.4 1 Contro l Room Area Ventil at i on Ai r Con dit i on i ng (AC) System............................... 3. 7. 5 1 Main Condenser Off gas.................................... 3. 7. 6 1 Main Turbine Bypass System............................... 3. 7. 7 1 S p e n t F u e l S t o r a g e P o o l
\\J a t e r Le v e l...................... 3. 7. 8 1 ELECTR I CAL POW ER SYSTEMS AC Sources Operating..................................... 3.8. l 1 AC Sources Shut do*,m...................................... 3. 8. 2 1 Di ese l Fue l Oil and Start i ng Ai r......................... 3.8. 3 1 DC Sources Operat i ng..................................... 3.8.4 1 DC Sources Shutdo*,m...................................... 3. 8. 5 1 Battery Parameters....................................... 3.8. 6 1 Di str i but i on Systems Operat i ng........................... 3.8. 7 1 Di str i but i on Systems Shutdown............................ 3.8.8 1 REFUEL IN G OPERAT I ONS Refueli ng Equ i pment Inter l ocks........................... 3. 9. l 1 Refue l Pos i t i on One Rod Out I nter l ock.................... 3. 9. 2 1 Contro l Rod Position..................................... 3. 9. 3 1 Con t ro l Ro d Pos iti on I ndi ca ti on.......................... 3. 9.4 1 Contro l Rod OPERA BI LITY Refueli ng........................ 3. 9. 5 1 Reactor Pressure Vesse l (RPV) Water Level I rrad i ated Fue l................................................... 3. 9. 6 1 Reac t or Pressure Vesse l (R PV) Water Level New Fue l or Contro l Rods................................... 3. 9. 7 1 Re s i d u a l H e a t Remo v a l ( RH R ) H i g h \\J a t e r Le v e l............. 3. 9. 8 1 Res i du a l He a t Remo v a l ( RH R ) Lo.,, \\J a t e r Leve l.............. 3. 9. 9 1 SP ECI AL OP ERATIO NS Reactor Mode Sw i tc h I nter l ock Test i ng.................... 3. 10. l 1 Si n g l e Cont r o l Rod ',.'i t h d r a *v1 a l Hot Sh u t do ~m............... 3. 10. 2 1 Si n g l e Contro l Ro d l.'i th d r a *v1a l Co l d Shut d o*,m.............. 3. 10. 3 1 Si ng l e Contro l Rod Dr i ve (CRD)
Remova l Refueli ng...................................... 3. 10. 4 1 Mu l ti pl e Contro l Rod \\.'i th d r m1a l Refue l i n g................ 3. 10. 5 1 Con t ro l Ro d Tes ti ng Opera ti ng............................ 3. 10. 6 1 SHUTDOWN MARG IN (SDM) Tes t Refueli ng..................... 3. 10. 7 1 I nserv i ce Leak and Hydrostat i c Test i ng Operation......... 3. 10.8 1 (cont i nued)
LaSa ll e 1 an d 2 Amen dmen t No. 219/205
'1--
TA BLE OF CON TEN TS (cont i nue d )
~
DESI GN FEAT URES 4-:-+/-
Site Location............................................ 4. 0 1
~
Reactor Core............................................. 4. 0 1 4-:-3 Fue l Storage............................................. 4. 0 2
~
ADMI NI STRATIVE CONTROLS : Respons i bi li ty........................................... 5. 1 1 : Organ i zat i on............................................. 5. 2 1 : Un i t Staff Qua li f i cat i ons................................ 5. 3 1 :-4 Procedures............................................... 5. 4 1 Programs and Manua l s..................................... 5. 5 1 : Report i ng Requi rements................................... 5. 6 1
~
Hi gh Rad i at i on Ar ea...................................... 5. 7 1 LaSa ll e 1 an d 2 Amen dment
~J o
. 147/133
ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.7 Limerick Generating Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-39 and NPF-85 Revised Technical Specification Pages Limerick Unit 1 Limerick Unit 2 Index Index ii ii iii iii iv iv v
v vi vi vii vii viii viii ix ix x
x xi xi xii xii xiii xiii xiv xiv xv xv xvi xvi xvii xvii xviii xviii xix xix xx xx xxi xxi xxii xxii xxiii xxiii xx iv xx iv xxv xxv xxvi xxvi xxvii xxvii xxviii xxviii
SECTION +/-
~~~~~~~~~~~~~~~~~~:::::::::::::::*=+/-~+/-
ACT IO~ *. * * * * * * *..
I 1 +/-
LH4ERICK PLANAR EXPOSURE..............
..... +/- +/-
AVERAGE TION RATE.. ******.......
A A LI NEAR HEAT GENERA
+/- +/-
AVERAGE PLnNnR L CA LIBRATimL. * * * * * * * * * * * * * * * * * * * * *
+/- +/-
CHMHJE A
CH 'A, ~HJEL CHECK...............................
............ +/- +/-
CHANNEL FUNCTI n
O~J A L TEST * * * * * * *...................
+/- 2 CORE ALTERATimL..........
CORE OPERATING LIMITS REPORT....
.................... +/- 2
. +/- 2 DOSE EQUIVALENT I B+/-............
.................. +/- 2 INT EDTSP) * * * * * * *.......
2 DOIJNSCALE TRI p SET PO
................. +/-
IO~J ENERGY..............
2 EMERGENCY CORE TRIP SYSTEM RESPONSE TIME.....
COOLING SYSTEM
+/- 3 OF CYCLE RECIRCULATION PUMP
..... +/- 3 E~JD (DELETED) * * * * * * *......
(DELETED) * * * * * * *............
+/- 3
... +/- 3 HIGH ( PO'tJER)
TRIP SETPOINT EHTSP)...........
+/- 3 JO ENT! FI ED LEAKAGE... ~~;;. ~~~;O I NT E !TSP l....................
. +/- 3 INTERMEDIATE (POWER)
.................... +/- 3 SYSTEM RESPONSE TH4E............
......... +/- 3 ISOLATION ROD PATTERN.*******.......
+/- 3 LIMITING CONTROL
~JER A TION RATE............
+/- 4 LINEAR HEAT GEr n
FUNCTIONAL TEST...........
LOGIC SYSTE~1 U~JIT +/-
+
Amendment No.,
33 37, 66
+
t
-+-
+
SECTION DEF INITIONS (Continued)
-HB-a-LOW I POii ER I TR Ip SET PO I NT I LTS p I N\\Gf IDELETEDI
.............................. 1 4 MEMBERISI * ~~ - ~~; * ;~~:;~ *************************************** 1 4
~4APFAC( Fl (MAPLHGR FLO* L~. F. ~ C* T* O*............................... 1 4 llM R)............................. 1 4
~4APFAC(P)
(POL' ER DE nPENDENT MAPLHGR MULTIPL IER)
~4HH 1 4 MUM CRIT ICAL POl.'ER RATIO (MCPR)......
..................... 1 4 OFFSITE DOSE CALCULATION MANUAL............................... 1 4 OPERABLE OPERABILITY........................................ 1 4 OPERAT IONAL COND ITION COND ITION............................. 1 5 PHYS ICS TESTS PRESSURE BOLIN ~~~~. ~~~~~~~.............................. ******* 1 5 PRIMARY CONTA INMENT I NTEG~ ~ ;~ *................................ 1 5 PROCESS CONTROL PROGRAM
................................. 1 5
....................................... 1 5 RATED THER~4AL p~,~~~................................. * * * * * * * * *
- 1 6 REACTOR ENCLOSURE s~~~~ ~~~~ *............................... * *
- l 6 CONTA INMENT INTEGRITY PURGE PURGHJG REACTOR PROTECT ION SYSTEM RESPONSE TIME
............. 1 6
....................... 1 6 REFUELING FLOOR SECONDAR~ *.................................... 1 6 CONTAINMENT INTEGRITY RECENTLY IRRADI ATED FUEL
............... 1 6 RESTRICTED AREA 1 7 IDELETEDI
............................................... 1 7 SHUTDOIJN ~~~~~ ~ :J....................................... * * * * * * *
- 1 7
............................................... 1 7 REPORTABLE EVENT SOURCE CHECK. :::::::::::::::::::....................... ******* 1 7
.............................. 1 7 SITE BOUNDARY LIMERICK UN IT l Amendment
~J o
. 33. ~
' 52 ' 66 ' 192 ' 207
SECTION DEF INI TIONS (Continued)
STAGGERED TEST BASI M
S.......................................... 1 8 THERMAL PO'i.JER TURBHJE BYPAS~. ~~~;~ ~~. ~~~~~ ~ ~~. ; ~ ~~~.................... * * * * * *
- 1 8
........................... 1 8 UNI DENTI FIED LEAKAGE.......................................... 1 8 UNRESTRICTED AREA II A
- 1 8 oENT ILnTION EXHAUST TREATMENT SYSTEM
.............................. 1 9 Table 1. 2' Onerati ona1 C t'
l onditions....................................... 1 10 LIMERICK UNIT l Amendment No. 66
SAFETY LIMITS AND LIMITINc
_o SAFETY SYSTEM SETTINGS SECTION
~ SAFETY LIMITS THER~1AL PO'*'ER L
O'vJ Pressure or Lm,* Flo*,
THER~1AL PO'*'ER H
- h
- * * * * * * * * * *
- 2 1 1gn Pressure and HigR Flow Reactor Coolant: Svstem p
....... * * * * * * * * * * * * * * * ** 2 1 J
i::
m ress ure................................... 2 1 Reactor Vessel IJat:er Level........................................ 2 2 LIMITING SAFETY SYSTEM SETT IN GS Reactor Protection S yst:em Inst:rument:at:ion S et:poi nt:s............... 2 3 Table 2. 2. 1 1 R eact:or Protection System Inst:rument:at:ion Set:point:s..................... 2 4
~ SAFETY LH1ITS THER~1AL PO' 'ER L
O'vJ Pressure or Lo*, Flo*,
VY vv
- * * * * * * * * * * * * * * * * * * * * * * * * ** B THER~1AL POER H. h 2 1 1gn Pressure and HigR Flow Left IAteAti "" 11 y 81 aAk
........................ 8 2 2 Left IAteAti "" 11 y 81 aAk 8 2 3 8
Reaetae GaalaAt System Peess*ee 2 4
................................... 8 2 5 Reactor Vessel IJat:er Level 8 2 5 LIMITING SAFETY SYSTEM SETT INGS Reactor Protection System Inst:rument:at:ion Set:point:s............... 8 2 6 LIMERICK UNI T l Amendment: No. 7, 33 +-
LIMIT I NG
~
ri
+NBH SURVEILLANCE REQUIREMENTS COND I TI ONS FOR OPERAT I ON AND REACTIVITY CONTROL SYSTEMS
.............. 3/ 4 1 1 Y4.lc SHUTDOWN MARGIN ********.........................
314 1 1 3/ 4. 1. 1 Y"A N0~1 A L I ES..........................................,
3/ 4. 1. 2 REACT I VI T n -
3/ 4. 1. 3 cmJTROL RODS
.... 3/ 4 1 3 El Operability................................. ::.... 3/ 4 1 6 CoAtrol RoEl Average Scram
... 3 1 ~ 1 8 p Scram IAsertioA Times...............
' ~ 1 9 CoAtrol I AElicatioA.............................
3
- 4 1 15 CoAtrol RoEl Dri ve Housi Ag 3/ 4. 1. 4 CONTROL ROD PROGRAM CONTROLS
.. 3/ 4 1 16 A Miflimizer. * * * * * * * * * * * * * * * * * * * *....................
3/ 4 1 18 RoEl ',fort RoEl Bl eek MoAitor * * * * * * * * * * * * * * * * * * * *........................ : 3/ 4 1 19 ROL SYSTE~1................................
3/ 4. 1. 5 ST ANDBY LI QUID CONT n
Ataborate Sol ut1 OA 3 1 5 1 SoElium Pe I
ntratioA 3 ' 4 1 21 cF~ig =u~r'-f'e'---3--:-'.
. ~.~r-r Temperature,-CoAcen eAtS 3 ' 4 1 22 Requ1 rem LEF;. ~~ A NK HJTENTIONALLY).....,
Deletes (
n 3/ 4.1. 1 5 3 14 2 2 "",
3 14 2 2.......
Al/ERA GE PLANAR LHlEnR H n t h 3 ' 4 2 6c Ras beCA 3/ 4 2 2 IAformati oA oA pag~ rn, refer to Aote oA page INTENTIONALLY OMIT LIMERICK UNIT l
~~ 37 AmeAElmeAt No.,
LIMITING COND ITIONS FOR OPERAT ION AND SURVEILLANCE REQUIREMENTS SECTION POWER DISTRIBUT ION LIMITS (Continued) 3/ 4.2.2 (DELETED)..................................................... 3/ 4 2 7 3/ 4.2.3 MINIMUM CRITICAL POWER RAT IO.................................. 3/ 4 2 8 Information on pages 3/ 4 2 10 thru 3/ 4 2 11 has been INTENTIONALLY OM ITTED, refer to Note on page 3/ 4 2 10......... 3/ 4 2 10 3/ 4.2.4 LINEAR HEAT GENERATION RATE................................... 3/ 4 2 12 3/ 4.3 INSTRUMENTATION 3/ 4.3.1 REACTOR PROTECT ION SYSTEM INSTRUMENTAT ION..................... 3/ 4 3 1 Table 3.3.1 1 Reactor Protection System Instrumentation............................. 3/ 4 3 2 Table 3.3.1 2 Reactor Protection System Response Times.............................. 3/ 4 3 6 Table 4.3.1.1 1 Reactor Protection System Instrumentation Surveillance Requirements................................ 3/ 4 3 7 LIMERICK UN IT 1
Amendment No. 7, 19, 33, 37, 66
+NBH LI MIT ING CO ND ITIO ~J S FOR OPERATimJ AND SlJRVEILLANCE REO lJ IRE M E~JTS SECTION INSTRUM ENTATION (Continued) 3/ 4.3.2 3/ 4.3.3 3/ 4.3.4 ISOLATION ACTUATION INSTRUMENTAT ION........................... 3/ 4 3 9 Table 3.3.2 1 Isolation Actuat ion Instrumentati on.......................... 3/ 4 3 11 Table 3.3.2 2 Isolation Actuation Instrumentation Setpoi nts................ 3/ 4 3 18 Table 3.3.2 3 Isolation System Instrumen tati on Response Ti me..................... 3/ 4 3 23 Table 4.3.2.1 1 Isolati on Act uati on Ins t rumen t ati on Surveill ance Requ i rements........................... 3/ 4 3 27 EMERGENCY CORE COOLING SYSTEM ACTUATION HJSTRUME ~JTATimJ............................................... 3/ 4 3 32 Table 3.3.3 1 Emergency Core Cool i ng System Actuation Instrumentation................ 3/ 4 3 33 Table 3.3.3 2 Emergency Core Cool i ng System Actuation Instrumentation Set points................................ 3/ 4 3 37 Tabl e 3.3.3 3 Emergency Co re Cooling Syst em Response Times........................... 3 / ~ 3 39 Table
~
. 3
. 3
. 1 1 Emergency Core Cool i ng System Actuati on Instrumentation Surveillance Requ i rements.............. 3/ 4 3 40 REC IRCULATION PUMP TRIP ACTUAT ION IN STRUMENTAT ION ATWS Reci rculat ion Pump Trip System Instrumentation........... 3/ 4 3 42 Table 3.3.4.1 1 ATWS Reci rculat ion Pump Trip System Instrumentat ion................. 3/ 4 3 43 Table 3.3.4.1 2 ATWS Reci rculat ion Pump Trip System Instrumentat ion Setpoi nts.............................. 3/4 3 44 Table 4.3.4.1 1 (Del eted).............................. 3/4 3 45 End of Cycl e Recirculat ion Pump Trip System Instrumentation............................................... 3/4 3 46 LIMERICK UNI T 1 Amendment No. 33, 186
LIMITING COND ITIONS FOR OPERAT ION AND SURVEILLANCE REQUIREMENTS SECTION INSTRUMENTATION (Continued) 3 / ~
. 3
. 5 Table 3.3.4.2 1 End of Cycle Recirculation Pump Trip System Instrumentation............ 3/4 3 48 Table 3.3.4.2 2 End of Cycle Recirculation Pump Trip Setpoints......................... 3/4 3 49 Table 3.3.4.2 3 End of Cycle Recirculation Pump Trip System Response Time.............. 3/ 4 3 50 Table 4.3.4.2.1 1 (Deleted)............................ 3/ 4 3 51 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION HlSTRUMHHATi mL.............................................. 3 1 ~ 3 52 Table 3.3.5 1 React or Core Isolation Cooling System Actuation Instrumenta ti on..................................... 3/ 4 3 53 Table 3.3.5 2 Reactor Core Isolation Cooling System Actuation Instrumentation Set points................................ 3/4 3 55 Table 4.3.5.1 1 (Deleted).............................. 3/ 4 3 56 3/4.3.6 CONTROL ROD BLOCK INSTRUMENTAT ION............................. 3/4 3 57 Table 3.3.6 1 Control Rod Block Instrumenta ti on...................................... 3/4 3 58 Table 3.3.6 2 Control Rod Block Instrumenta ti on Set points............................ 3/4 3 60 Figure 3.3.6 1 SRM Count Rate vs Signal to
~J oise Ratio.................................... 3/4 3 60b Table 4.3.6 1 Control Rod Block Instrumenta ti on Survei 11 ance Requirements............ 3/4 3 61 3/4.3.7 MON ITORING INSTRUMENTATION Radiation Monitoring Instrumentation.......................... 3/4 3 63 Table 3.3.7.1 1 Radiation Monitoring Instrumentation........................ 3/4 3 64 LIMERICK UN IT 1 Amendment No. ~4
. 186
LIMITING COND ITIONS FOR OPERAT ION AND SURVEILLANCE REQUIREMENTS SECTION 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 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 Shutdo*.. *n 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 (Deleted)............................ 3/ 4 3 83 Accident Monitoring Instrumentation......................... 3/ 4 3 84 Table 3.3. 7. 5 1 Accident Monitoring Instrumen tati on............................... 3/ 4 3 85 Table 4.3. 7. 5 1 Accident Monitoring Instrumenta ti on Survei 11 ance Requirements....... 3/ 4 3 87 Source Range Mani tors.......................................
This information from page 3/ 4 3 89 has been intentionally omitted.
Refer to note on page.......................................
3/ 4 3 88 3/ 4 3 89 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 LIMERICK UN IT 1 Amendment No
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. 75, 104, 117, 186
LIMITING COND ITIONS FOR OPERAT ION AND SURVEILLANCE REQUIREMENTS SECTION INSTRUMENTATION (Continued)
(Deleted)...................................................... 3/4 3 97 The information from pages 3/ 4 3 98 through 3/4 3 101 has been intentionall y omitted.
Refer to note on page 3/4 3 98....................... 3/ 4 3 98 The information from pages 3/4 3 103 through 3/ 4 3 108 has been intentional ly omitted.
Refer to note on page 3/ 4 3 103...................... 3/4 3 103 3/ 4.3.8 (Deleted)
The information on pages 3/ 4 3 110 and 3/ 4 3 111 has been intentionall y omitted.
3/4.3.9 Refer to note on page 3/ 4 3 110............... 3/ 4 3 110 FEEDWATER/ MAIN TURB INE TRIP SYSTEM ACTUAT ION HJSTRUMENTATION........................................... 3/ 4 3 112 Table 3.3.9 1 Feedwater/ Main Turbine Trip System Actuation Instrumentation.............. 3/ 4 3 113 Table 3.3.9 2 Feedwater/ Main Turbine Trip System Actuation Instrumen tati on Setpoi nts.............................. 3/ 4 3 114 Table 4.3.9.1 1 (Deleted)..................................... 3/ 4 3 115 Y-4-:-4 REACTOR COOLMH SYSTEM 3/ 4.4.1 REC IRCULATION SYSTEM Reci rcu l ati on Loops............................................. 3/ 4 4 1 LIMERICK UN IT 1 Amendment No. ~. 100, 161, 156, 1Bi, 228
LIMITING COND ITIONS FOR OPERAT ION AND SURVEILLANCE REQUIREMENTS SECTION REACTOR COOLANT SYSTEM (Continued)
Figure 3.4.1. 1 1 Deleted............................... 3/4 4 3 Jet Pumps..................................................... 3/4 4 4 Reci rcul ati on Pumps........................................... 3/4 4 5 Idl e Recirculation Loop Startup............................... 3/4 4 6 3/4.4.2 SAFETY/RELIEF VALVES.......................................... 3/4 4 7 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems..................................... 3/~
8 Operational Leakage........................................... 3/~
9 Table 3.4.3.2 1 Deleted............................... 3/4 4 11 3/4.4.4 (Deleted) The information from pages 3/4 4 12 through 3/4 4 14 has been intentionally omitted.
Refer to note on page 3/4 4 12................................ 3/4 4 12 3/4.4.5 SPECIFIC ACTIVITY............................................. 3/4 4 15 3/4.4.6 Table 4.4.5 1 Primary Coolant Specific Activity Sample and Analysis Program.............. 3/4 4 17 PRESSURE/TEMPERATURE LIMITS Reactor Coolant System........................................ 3/4 4 18 Figure 3.4.6.1 1 Minimum Reactor Pressure Vessel Metal Temperature Vs. Reactor Vessel Pressure....................... 3/4 4 20 Table 4.4.6.1.3 1 Deleted.............................. 3/4 4 21 Reactor Steam Dome............................................ 3/4 4 22 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES.............................. 3/4 4 23 3/4.4.8 (DELETED)..................................................... 3/4 4 24 LIMER ICK UN IT 1 Amendment No. 1§7
, 1 7~
, 177
, 1 82
, 199
-llHl8f SURVEI LLA! CE FOR OPERAT ION AND LIMITING COND ITIONS REOUIREME~HS REACTOR Cold Shutdown........
COOLA~~H~~~~~~~A:i:tA~L~~~~~~=:::::::::::::::::::::3:,14::4=2:5 L HE AT REn on RESIDUA-3,14 4 26 d *n Hot Shut ow SYSTEM (Continued)
EMERGE~JCY CORE COOLHJG SYSTEMS 3/ 4.5.2 LH4ERICK EGGS A
OP ERATING..........
EGGS SHUTDOWN.....
SUPPRESSION CHAMBER 3/ 4 5 1 3/ 4 5 6 3/ 4 5 8 3/ 4 6 1
, Containment n1 A" p Lock. *******
3/ 4 6 7 P" mar;
- " Pat A11ay * * "
314 6 8 AltePnate DPa1 MSIV Leal<a§e "
Ate§eity......
Conta1nmen p ssuPe * * * * * *
- t StPuctuPal I
... 3 / ~ 6 9 PPimaP)'
b P IntePnalPe A. P TempePatuPe * * * * *
... 3/ 4 6 11 Deyuell Aveea§e "'
System ************
ChambeP PuPge
, 1 i_-'l-A~S=uppPe5Sl on SYSTEMS U~JIT 1 3/ 4 6 12 3/ 4 6 15 3/ 4 6 16 Amendment No.
33 Hl7 ' 146
LIMITING CON DI TIONS FOR OPERAT ION AND SURVE I LLANCE REQU IREMENTS SECTION CONTA INM ENT SYSTEMS (Continued) 3/4.6.4 VACUU ~~ RELi EF Suppress ion Chamber Dry'vi'el l Vacuum Breakers..................... 3/4 6 44 3/4.6.5 SECO NDARY CONTA INM ENT Reactor Encl osure Secondary Cont ai nment Integrity................. 3/ 4 6 46 Refueli ng Area Secondary Cont ai nment Int egrity.................... 3/ 4 6 47 React or Encl osure Secondary Conta i nment Automati c I sol ati on Va l ves.................................................. 3 / ~ 6 ~8 Refuel ing Area Secondary Containment Automati c I sol ati on Va l ves.................................................. 3 / ~ 6 50 Standby Gas Treatment System Common System...................... 3/ 4 6 52 Reactor Enclosure Recirculati on System............................ 3/ 4 6 55 3/4.6.6 PR IMARY CONTA INMENT ATMOSPHERE CONTROL Del eted........................................................... 3/ 4 6 57 1
Drywel l Hydrogen Mi xi ng System.................................... 3/ 4 6 58 Drywel l and Suppressi on Chamber Oxygen Concentration.............. 3/ 4 6 59 3/ 4.7 PLANT SYSTEMS 3/ 4.7.1 SERV ICE WATER SYSTEMS Res idual Heat Remova l Servi ce Wa t er Syst em Common System............................................................ 3/ 4 7 1 Emergency Servi ce Wa t er Syst em Common System.................... 3/ 4 7 3 Ultima t e Heat Si nk................................................ 3/ 4 7 5 LIM ERICK UNI T 1 Amendment
~J o
. 27, 4Q, Hl5, 173
LIMITING COND ITIONS FOR OPERAT ION AND SURVEILLANCE REQUIREMENTS SECTION PLANT SYSTEMS (Continued) 3/ 4. 7. 2 CONTROL ROOM EMERGENCY FRESH AIR SUPPLY SYSTEM COMMON SYSTE~~........................................................ 3/ 4 7 6 3/ 4. 7. 3 REACTOR CORE ISOLAT ION COOLING SYSTEM......................... 3/ 4 7 9 3/ 4. 7. 4 S~JUBBERS...................................................... 3/ 4 7 11 Figure 4. 7.4 1 Sample Plan 2) For Snubber Functiona l Test.......................... 3/ 4 7 16 3/ 4. 7. 5 SEALED SOURCE cmnAMHJATimJ................................... 3/ 4 7 17 3 1 ~
. 7. 6 DELETED; Refer to note on page................................ 3 1 ~ 7 19 3 1 ~
. 7. 7 DELETED; Refer to note on page................................ 3 1 ~ 7 19 3/ 4. 7.8 MAHJ TURB INE BYPASS SYSTEM.................................... 3/ 4 7 33 Y-4-: ELECTRICAL POl.'ER SYSTEMS 3/ 4.8. 1 A.G. SOURCES A. C. Sources Operating................................... 3/ 4 8 1 Table 4.8. 1.1. 2 1 DELETED..................................... 3/ 4 8 8 A. C. Sources Shutdo*,m.................................... 3/ 4 8 9 3/ 4.8. 2 D.C. SOURCES D. C. Sources Operating................................... 3/ 4 8 10 LIMERICK UN IT 1 Amendment No. 33,
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1 0~
. 189
LIMITING COND ITIONS FOR OPERAT ION AND SECTION SURVEILLANCE R EOU IREME~HS ELECTRICAL p 3/ 4.8.3 3 / ~
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. ~
OIJER SYSTEMS ( c ont1nued)
Re:q~u~i ~re~m*e~n+t~
s -:--:-:_;:_~nc~e~-:-:-;-:-;--:-:-:-:-:-:-:--:--:-:--31!.4-.Q-:~
D C S
=.
ources Shutdmm.
- * * * * * * * * * * *
- 3/ 4 8 13 Table 4.8.2. 1 1 Battery Surveilla ONS ITE POIJER DISTRIBUTIO ~J
.............................. 3/ 4 8 14 r SYSTEMS Distribution Operating........
D
. t 15 ribution Shutdown
- * * * * * * * * * *
- 3/ 4 8 15 ELECTRICAL E8UIPMEMT
- ri - r1-PROT
.... * * * * * *
- 3/ 4 8 18 ECTIVE DEVICES (Deleted).................................................. 3 / ~ 8 21 (Deleted)........................................
S~ stem Electric
.......... 3 1 ~ 8 2' Reactor Protect
- lOn Pm,*er Monitoring
...... 3/ 4 8 28
-3+4-: REFUELHJG OPERATimJS 3/ 4.9.1 3/ 4.9.2 3/ 4.9.3 3/ 4.9.4 3/ 4.9.5 3/ 4.9.6 3 / ~
. 9
. 7 LH4ERICK REACTOR MODE SW ITCH
................................ 3/ 4 9 1 INSTRUMENTATION............................................ 3/ 4 9 3 CONTROL ROD POS ITION..........
............................... 3/ 4 9 7 REFUELING PLATFORM
................................ 3/ 4 9 8 CRMJE TR A\\'EL M V SPENT FUE L STORAGE POOL......... * * *
- 3 I
........ d 9 10 "ATE "n R LEVE L 3
/ 4 9 12 SPENT FUEL STORAGE POOL
............. 3 / ~ 9 11 REACTOR VESSEL...
"'ATER i\\11 LEVEL U~JIT 1 Amendment No. 93 209
LIMITING COND ITIONS FOR OPERAT ION AND SURVEILLANCE REQUIREMENTS SECTION REFUELING OPERATIONS (Continued )
3/4.9.10 CONTROL ROD REMOVAL Single Control Rod Removal................................. 3/4 9 13 Multiple Control Rod Removal............................... 3/4 9 15 3/ 4.9. 11 RES IDUAL HEAT REMOVAL AND COOLANT CIRCULAT ION High IJater Level........................................... 3/ 4 9 17 Lo*,, \\Jater Level............................................ 3/ 4 9 18 3/ 4.10 SPEC IAL TEST EXCEPT IONS 3/ 4.10.1 PRIMARY CONTA INMENT INTEGRITY.............................. 3/ 4 10 1 3/ 4.10.2 ROD \\.'ORTH MHWH ZER........................................ 3/ 4 10 2 3/ 4.10.3 SHUTDOWN MARG IN DEMONSTRAT IONS............................. 3/ 4 10 3 3/ 4.10.4 RECIRCULATimJ LOOPS........................................ 3/ 4 10 4 3/ 4.10.5 OXYGEN CONCENTRAT ION....................................... 3/ 4 10 5 3/ 4.10.6 TRAHJ me STARTUPS.......................................... 3/ 4 10 6 3/ 4.10.7 RESERVED CURRENTLY NOT USED.............................. 3/ 4 10 7 3/ 4.10.8 INSERVICE LEAK AND HYDROSTATIC TESTING..................... 3/ 4 10 8 3/ 4.11 RADIOACT IVE EFFLUENTS 3/ 4.11.1 3/ 4.11.2 LIQUID EFFLUENTS The information from pages 3/ 4 11 1 through 3/ 4 11 6 has been intentionally omitted.
Refer to note on page 3/4 11 1................... 3/ 4 11 1 Liquid Holdup Tan ks........................................ 3/ 4 11 7 GASEOUS EFFLUENTS The information from pages 3/ 4 11 8 through 3/ 4 11 14 has been intentionally omitted.
Refer to note on page 3/ 4 11 8................... 3/ 4 11 8 LIMERICK UN IT 1 Amendment
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. 17, 33, ~
, 133
LIMITING COND ITIONS FOR OPERAT ION AND SURVEILLANCE REQUIREMENTS SECTION RAD IOACTIVE EFFLUENTS (Continued) 3/ 4. 11.3 3/ 4. 11. 4 3/ 4. 12 The information from page 3/ 4 11 15 has been intentionall y omitted.
Refer to note page 3/ 4 11 15............................... 3/4 11 15 Main Condenser............................................. 3/4 11 16 The information on page 3/4 11 17 has been intentionally omitted.
Refer to note on this page.................................................. 3/ 4 11 17 (Deleted) The information on pages 3/ 4 11 18 through 3/ 4 11 20 has been intentionally omitted.
-R-e-fe.r.
to note on page 3/ 4 11 18.
(Deleted).................................................. 3/ 4 11 18 (Deleted) The information on pages 3/ 4 12 1 through 3/ 4 12 14 has been intentional ly omitted.
Refer to note on page 3/ 4 12 1................... 3/ 4 12 1 LIMERICK UN IT 1 Amendment No. ~
, 228
SECTION 3/ 4. 0 APPLICABI LIT¥..................................................... B 3/ 4 0 1 3/ 4.1 REACT IVITY CONTROL SYSTEMS 3/ 4.1. 1 SHUTDO'tJN MARGIN B 3/ 4 1 1 3/ 4.1. 2 REACTIVITY AN OMA LI ES B 3/ 4 1 1 3/ 4.1. 3 cmnROL RODS B 3/ 4 1 2 3/ 4.1. 4 cmnROL ROD PROGRAM cmnROLS B 3/ 4 1 3 3/ 4.1. 5 STANDBY LIQUID cmHROL SYSTEM B 3/ 4 1 4 3/ 4.2 POWER DISTRIBUT ION LIMITS 3/ 4.2.1 AVERAGE PLANAR LINEAR HEAT GENERAT ION RATE........................................................ B 3/ 4 2 1 3/ 4.2.2 (DELETED)................................................... B 3/ 4 2 2 LEFT HHrnTimJALLY BLMJK................................................ B 3/4 2 3 3/ 4.2.3 MHJIMUM CRITICAL POIJER RATIO................................ B 3/ 4 2 4 3/ 4.2.4 LINEAR HEAT GENERAT ION RATE................................. B 3/ 4 2 5 Y-4-: rn STRUM E
~HATI mi 3/ 4.3.1 REACTOR PROTECT ION SYSTEM INSTRUMENTAT ION................... B 3/ 4 3 1 3/ 4.3.2 ISOLATION ACTUATION INSTRUMENTAT ION......................... B 3/ 4 3 2 3/ 4.3.3 EMERGENCY CORE COOL ING SYSTEM ACTUAT ION HJSTRUME~HATimJ............................................. B 3/ 4 3 2 3/ 4.3.4 REC IRCULATION PUMP TRIP ACTUAT ION INSTRUMENTAT ION........... B 3/ 4 3 3 3/ 4.3.5 REACTOR CORE ISOLAT ION COOLING SYSTEM ACTUAT ION HJSTRUME~HATimJ............................................. B 3/ 4 3 4 3 / ~
. 3
. 6 cmnRO L ROD BLOCK HJSTRU~1E~HATimJ........................... B 3 / ~ 3 ~
3 / ~
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. 7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation...................... B 3/ 4 3 5 LIMERICK UN IT 1 Amendment No. 7, 33, 66, 69
SECTION 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 ~4onitors...................................... B 3/ 4 3 5 (Deleted).................................................. B 3/ 4 3 6 Chlorine and TOJ(i c Gas Detection Systems................... B 3/ 4 3 6 (Deleted).................................................. B 3/ 4 3 6 (Deleted).................................................. B 3/ 4 3 7 (Deleted).................................................. B 3/ 4 3 7 (Deleted).................................................. B 3/ 4 3 7 3/ 4.3.8 (Deleted).................................................. B 3/ 4 3 7 3/ 4.3.9 FEEDIJATER/f4AIN TURBINE TRIP SYSTEM ACTUATimJ INSTRUME~HATimJ............................................ B 3/ 4 3 7 Bases Figure B 3/ 4.3 1 Reactor Vessel 'tJater Le vel....................... B 3/ 4 3 8 3/ 4.4 REACTOR COOLANT SYSTEM 3/ 4.4. 1 RECIRCULATimJ SYSTEM....................................... B 3/ 4 4 1 3/ 4.4.2 SAFETY / RELi EF VALVES....................................... B 3/ 4 4 2 3/ 4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems.................................. B 3/ 4 4 3 Opera ti on al Leakage........................................ B 3/ 4 4 3 3/ 4.4.4 CHEMISTRY.................................................. B 3/ 4 4 3 LIMERICK UNIT 1 Amendment
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, 75,
104 ' 117 ' 131, 153 ' 228
SECTION REACTOR COOLANT SYSTEM (Conti nued )
3/4.4. 5 3/4.4. 6 SPECIFIC ACTIVITY PRESSURE / TEMPERAT~~~. ~ ~ ~~ ~ ;~................................... B 3/4 4 4 Bases Table B 3/4.4. 6 *1**********************************
B 3/4 4 4 Reactor Vessel Bases Figure B 3/ 4.4. 6 1 Toughness........ * * * * * * * * * * * * *
- B 3/4 4 7 Fast Neutron Fluence (E>l ~eV) At 1/ 4 T As A Function of Service Life...
3/ 4 4 8 3 / ~. ~. 7 MAIN STEAM LINE ISOLATION VALVES
........................ B 18ELETED )
- * * * * * * * * * * * ** * * * * * * * * * * * * * * *
- B 3f 4 4 6 3 / ~
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. 8
...................................... * * * * * * * * * * * *... B 3 / ~
~ 6 RES IDUAL HEAT REMOVAL Y-4-: EMERGE~lCY CORE COOLHJG S;~;~~~~................................... B 3/4 4 6 3/4.4. 9 3/ 4. 5. 1 and 3/ 4. 5. 2 EGGS OPERAT ING and SHUTDOWN
')I~ c.
. *. *. *. *. *. *. *. *. *. *. *. **. *. *. *. *. *.
- B 3/ 4 5 4
~
CONTAINMENT SYSTEMS 3/ 4. 6. 1 PRIMARY CONTA INMENT Primary Containment Integrity.............. * * * * * * * * * * * *
- B 3/ 4 6 1 Primary Containment Leakage
. *. *. *. *. *. *. *. * * * * * * * * * * * * *
- B 3/ 4 6 1 Pr1marv Genta
- t J
inmen Structural Integrity..........
......................... B 3 11 ~ 6 2 Dryh'Cl l d S anuppression Chamber Purge S 3/4. 6. 2 B 3 ' 4 J
6 3 LIMERICK UN IT 1 Amendment No
~ 199 Associ ated with Amen~men f 216
SECTION................................................................. PAGE CONTA INMENT SYSTEMS (Continued) 3/4.6.3 PRIMARY CONTA INMENT ISOLAT ION VALVES................. B 3/4 6 4 3/4.6.4 VACUU~4 RELIEF........................................ B 3/4 6 4 3/4.6.5 SECONDARY CONTA I NME~JT................................ B 3/4 6 5 3/ 4.6.6 PRIMARY CONTA INMENT ATMOSPHERE CONTROL............... B 3/ 4 6 6 Y-4-:-f.
PLMJT SYSTrnS 3/ 4.7.1 SERV ICE l.'ATER SYSTEMS COMMON SYSTrnS............... B 3/ 4 7 1 3i'4. 7. 2 CO~JTROL R00~4 E~4ERGE~J CY FRESH A+/-R SUPPLY SYSTE~4 cm4MmJ SYSTrn........................................ B 3/ 4 7 la 3/ 4.7.3 REACTOR CORE ISOLATimJ COOLING SYSTEM................ B 3/ 4 7 le 3/ 4.7.4 SNUBBERS............................................. B 3/ 4 7 2 3/ 4.7.5 SEALED SOURCE CON TAM I ~JAT I mJ.......................... B 3/ 4 7 3 3 / ~
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. 6 (Deleted)............................................ B 3 / ~ 7 3 / ~
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. 7 (Deleted)............................................ B 3 / ~ 7 3 / ~
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. 8 MAI ~J TURB HJ E BYPASS SYSTEM........................... B 3 / ~ 7 5
.3-f.4-:-8 ELECTRICAL POIJER SYSTH4 3/4.8.1, 3/4.8.2, and 3/4.8.3 A.G. SOURCES, D.C. SOURCES, AND ONS ITE POWER DISTRIBUT ION SYSTEMS................................. B 3/4 8 1 3/4.8.4 ELECTRICAL EQU IPMENT PROTECT IVE DEV ICES.............. B 3/4 8 3
-3+4-: REFUEL ING OPERATIONS 3/4.9. l REACTOR MODE SW ITCH.................................. B 3/4 9 1 3/4.9.2 INSTRUMENTATION...................................... B 3/4 9 1 3/4.9.3 CONTROL ROD POSITION................................. B 3/4 9 1 3/4.9.4 DECAY TIME........................................... B 3/4 9 1 3/4.9.5 Cm4MU~HCATIONS....................................... B 3/4 9 1 LIMERICK UN IT 1 Amendment No. 27, ~o
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SECTION REFUEL I NG OPERATIONS (Cont i nued )
3/ 4.9.6 REFUELHJG PLATFORM................................... B 3/4 9 2 3/ 4.9. 7 CRANE TRAVEL SPENT FUEL STORAGE POOL............... B 3/4 9 2 3/ 4.9.8 and 3/ 4.9.9 IJATER LEVEL REACTOR VESSEL and WATER LEVEL SPENT FUEL STORAGE POOL............ B 3/4 9 2 3/ 4.9. 10 CONTROL ROD REMOVAL.................................. B 3/ 4 9 2 3/ 4.9. 11 RES I DUAL HEAT REMOVAL AN D COOLANT CI RCULAT I ON........ B 3/ 4 9 2 3/ 4. 10 SPEC I AL TEST EXCEPTI ONS 3/ 4. 10. l PRIMARY cmJTA I ~JM ENT HJTEGRITY........................ B 3/ 4 10 1 3/ 4. 10.2 ROD \\.'ORTH M I ~J IM I ZER.................................. B 3/ 4 10 1 3/ 4. 10.3 SHUTDO\\m MARG HJ DE~1mJ STRATIONS....................... B 3/ 4 10 1 3/ 4. 10.4 REC IRCU LAH mJ LOOPS.................................. B 3/ 4 10 1 3/ 4. 10.5 OXYGE~J cmJCENTRAT i mJ................................. B 3/ 4 10 1 3/ 4. 10.6 TRAHJHJG STARTUPS.................................... B 3/ 4 10 1 3/ 4. 10.7 RESERVED CURRE~JTLY ~JOT USED........................ B 3/ 4 10 1 3/ 4. 10.8 HJSERV I CE LEAK Mm HYDROSTATIC TESTHJG............... B 3/ 4 10 2 3/ 4. 11 RAD I OACT I VE EFFLUENTS 3/ 4. 11. l LIQUID EFFLUENTS The i nformati on on page B 3/ 4 11 1 has been i ntenti ona l ly omi tted.
Refer to note on th i s page... B 3/ 4 11 1 (Deleted)............................................ B 3/ 4 11 2 Liqu i d Holdup Tan ks.................................. B 3/ 4 11 2 3/ 4. 11.2 GASEOUS EFFLUENTS (Deleted)............................................ B 3/ 4 11 2 The information on page B 3/ 4 11 3 has been intentiona l l y omitted.
Refer to note on this page... B 3/ 4 11 3 (Deleted)............................................ B 3/ 4 11 4 LI MERI CK UN I T 1 Amendment
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SECTION RADI OACTIVE EFFLUENTS (Continued)
(Deleted l The information from page B 3/4 11 4 has been intentionall y omitted.
Refer to note on page B 3/ 4 11 4............. B Main Condenser.......................................... B (Deleted)............................................... B 3/ 4. 11. 3 (Deleted)............................................... B 3/ 4. 11. 4 (Deleted)............................................... B 3/ 4. 12 (Deleted)
The information from pages B 3/ 4 12 1 through B 3/ 4 12 2 has been inten tionally omitted.
Refer to note on 3/4 11 4 3/4 11 5 3/ 4 11 5 3/ 4 11 5 3/ 4 11 5 page B 3/ 4 12 1.............................. B 3/ 4 12 1 LI MER I CK UN I T 1 Amendment No. ~
, 228
SECTION :-+/--
-s+ff E)(clus i on Area 5 1 Le11 Pee el at; ee Zeee
- * * * * * * * * * * * * * * * * * * * * * * * *. S 1 Fi§eFe S.;:;* ;*...................................... * * * *
- S I F i gu~~ * ~~ ~ ~ ~ * ~ *...................................... * * * *
- E>(Cl us i on Area Low Populat i on Zone Maes DefiAiA§ UNRESTRICTE
. *... *..*... *... *...
- s 3 for Rad i oactive Gaseous a~d n RL~n S _ and SI TE BOU NDARY i qu1d Effluents Fi gure 5. 1.3 la Ma D f..
Radi oact1* i.*e Gasco pc i _ni ng U~JRESTR I CTED ' RE ' S
--- us and L
- d n
n for iqu1 Effl uents (De l eted)
. ~~~ * ~~~~~~ * ~~ * ~~~~ * ~ * ~ * ~~~ * ~~~~ *..........................
omitted.
Refer to note on intentiona l ly page 5 6......................
Figure 5. 1.3 lb M
Radioact i ve Gase ap Defi _nin_g U~JRESTRICTED ' RE ous and L1qu1d Effl uents n
AS for : CONTAHJ~1 E ~H 5 1 5 5 5 1 5 6 Configurati on Design Temper~~~;~ * ~n* d*.P................ *. * * * * * * * * * * * * * * * * * * * * * * * * *.. 5 1 res sure Seceedary Ce eta i emeet
. *... *... *... *... *...... *... *... *...
- S I 5
- 3 REACTOR CORE
.................................... * * * * * * * * * *
- 5 7 Fuel Assembl i es Control Rod Ass~~ ~l* i* ~~................... * * * * * * * * * * * * * * * * * * * * * * *
- 5 7 :-4 REACTOR COOLMH SYSTE ~;............................................. 5 7 Design Pressure and Temperature Vol ume
....... * * * * * * * * * * * * * * * * * * * * * * * * * * *... 5 7 FUEL ~;~~;~~........................................... * * * * * * * * * * *. 5 8 Cri t i cal i ty......................................................... 5 8 LI MERI CK UNI T l Amendment No. 48
SECTION FUEL STORAGE (Cont i nued)
.... 5 8 LIMIT.. **********
COMPONENT CYCL IC OR TRANS IENT
. t Limits........ 5 9 t Cycl ic or Trans1en Table 5.6. 1 1 Componen LIMERICK UN IT l
ADM I NI STRAT I VE CONTROLS M
.. 6 1 ORGANIZATION.........
~
' ND DNSITE ORGAN IZATION..........
..... 6 3 6
') 1 OFFSITE M El
. c.
1 Delet e....
Figure 6. 2. 1
............ 6 2 6 4 T ST A FF...............
- 6. 2. 2 UNI n
Delet:eEl..................
Figure 6. 2. 2 1 Table 6. 2. 2 1 MiAilflUlfl ShiH Cre*vr
............ 6 5 ColflposHi OA............
6
............................ 6 A page * * * * * * *
- 6 6 Refer t:o AOt e o 6. 2. 3 DELETED; -
'I' AL ADllISOR...........................
6 6
- 6. 2. 4 SHIFT TECHNICn " '
- * * * * * * * * * * * *** * * * * * * * * * * * * * * :::: 6 UN I T STAFF QUALIFICAT I ONS.........
7 :-3 l::E=tE8
'6-:-4 DE
- * * * : DELETED Delet:eEl Delet:eEl
................ 6 7
.... 6 7 6 7
- :::: : : : : : : :............. : : : : : : : : : : : : : 6 7 Del et:eEl Del et:eEl. * * * : : : : : : : : : : : : : : : : : : : : : : : : :....................... 6 9 Del et:eEl * * * *
..... 6 8 LI MERI CK UN I T l AlfleAEllfleAt: No. 33, 35, 96, 160, 176
ADM I NI STRAT I VE CONTROLS SECTION :-5-: Deleted Deleted.................................................... 6 9 Deleted.................................................... 6 9 Deleted Deleted.................................................... 6 10 Deleted.................................................... 6 10 Deleted.................................................... 6 10
.................................................... 6 10 Deleted.................................................... 6 10 Deleted.................................................... 6 12 Deleted
.fr::j-SAFETY LIMIT VIOLATION................................... * * * * * * * * *
- 6 12a REPORTABLE EVE~J; * ;~;;~~:.................................. * * * * * * * * *
- 6 12 :-8 PROCEDURES MJD PROGR' MS............................................ 6 12a M
- * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- 6
- ..,.<)
RE PORT! NG REQU !REM EN TS 13
~
ROUTINE REPORTS............................................ 6 15 Startup Report.....
6 Moot Al Y O~e rati "§ Re~o rts 15
.................................. 6 16 Anrwal Rad1olo.,,
- l
- i"'l ca EAvi rOAITleAtal Opera ti A§ Report......... 6 16 AAAual Radioactive EfflueAt Release Report................. 6 17 CORE OPERATING LIMITS REPORTS * * * * * * * * * * * * * * * * * * * * * * * * * * * *.. 6 18a :-1 DELETED
................................. * * * * * * * * * *
- 6 18a
~
RAD I ATI~~: * ~~~;~~; ; ~~: * ~~~~~~~~............................ * * * * * * * * *
- 6 19 :-1 HI GH RADIATimJ ' RE '
............................. * * * * * * * *
- 6 20 H
H * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- 6 20 SPECIAL REPORTS LI MERI CK UN I T l AmeAdffieAt No. 37,
~7
. 96, 176, 192
ADMINI STRAT I VE CONTROLS SECTION :-H-PROCESS CONTROL PROGRAM E PCP)..................................... 6 21 : OFFSITE DOSE CALCULATION MANUAL EODCM)............................ 6 22
- 6. 15 EDel eted)......................................................... 622 :-tt;.
CONTROL Rom~ ENVELOPE HABITABI LIT¥ PROGRAM........................ 6 22 :-1+
SAFETY FU ~J CTIO N DETER~H NATimJ PROGRAM E SFDP)...................... 6 23 LI MERI CK UNI T 1
)()(V i i i Amen dment
~J o..i+.g, i gg, 219
SECTION
~
-H-
-H-h4
+-:-&
~
-+/--..,-7.
+-:--AA h8-h9-h9-a-
+-:-H}
+-:-+/-+
-+/--:-+/- -+/--:-8
-+/--:-1-4
-+/---:-+&
+-:-l-&a-h.ffl
-h+&a-
+-:+f.
+-:-+&
+-:-+9-h2B ACT I O~J........................................................ 1 1 AVERAGE PLANAR EXPOSURE....................................... 1 1 AVERAGE PLANAR LINEAR HEAT GENERAT ION RATE.................... 1 1 CHMHJEL CALIBRATimJ........................................... 1 1 CHMHJEL CHECK................................................. 1 1 CHMHJEL FUNCTimJAL TEST....................................... 1 1 CORE ALTERATimJ............................................... 1 2 CORE OPERATING LIMITS REPORT.................................. 1 2 CRIT ICAL PO'tJER RATIO.......................................... 1 2 DOSE EQU IVALENT I 131......................................... 1 2 DOIJNSCALE TRIP SET POINT EDTSP)................................ 1 2 E AVERAGE DISHHEGRATimJ rnERGY.............................. 1 2 EMERGENCY CORE COOLING SYSTEM (EGGS) RESPONSE TIME............ 1 2 END OF CYCLE REC IRCULAT ION PUMP TRIP SYSTEM RESPONSE TIME..... 1 3 (DELETED)..................................................... 1 3 (DELETED)..................................................... 1 3 FREQUrnCY NOTATimJ............................................ 1 3 HIGH (POIJER) TRIP SETPOHH (HTSP)............................. 1 3 IDE~H I F I ED LEAKAGE............................................ 1 3 INTERMED IATE (POWER) TRIP SETPO INT (ITSP)..................... 1 3 ISOLAT ION SYSTEM RESPONSE TIME................................ 1 3 LIMITING CONTROL ROD PATTERN.................................. 1 3 LINEAR HEAT GENERAT ION RATE................................... 1 3 LOG IC SYSTEM FUNCTIONAL TEST.................................. 1 4 LIMERICK UN IT 2
+
AmeAdmeAt No. 4, 48
SECTION DEF INITIONS (Continued)
-HB-a-
~~EMBER( S). ~~. ;;;. ~~~: ; ~..*...*..*...*...*...*...*...*. * * * * * *
- 1 4 MAPFAC( Fl 04APLHGR FLO.'.>. F. ~ C* T* O*.............................. 1 4 A
R)
(DELETED)
............................ 1 4 MAPFAC(P)
(POWER DE PENDENT MAPLHGR MULT IPLIER)
MIN IMUM CRITICAL POllER RATIO (MCPR).....
. *..*... *...
- 1 4 1 4 OFFS ITE DOSE CALCULATION MANUAL
.............................. 1 4 OPERAB LE OPERABILITY....................................... 1 4 OPERATIONAL CON DITION COND ITION............................ 1 5 PHYS ICS TESTS PRESSURE BOLIN ~~~~
. ~~~~~~~.............................. ****** 1 5 PRIMARY CONTAINMENT I NTEG~ ~ ;~ *............................... 1 5
................................ 1 5 PROCESS CONTROL PROGRAM...................................... 1 5 PURGE PURG ING RATED THERfML P~ l*J~~.......................................... 1 6 REACTOR ENCLOSURE s~~~~~~~~ *............................ * * * *
- 1 6 CONTA INMENT INTEGRITY REACTOR PROTECTION SYSTEM RESPONSE TIME
............ 1 6
...................... 1 6 REFUELING FLOOR SECON DAR~.................................... 1 6 CONTA INMENT INTEGRITY RECENTLY IRRAD IATED FUEL
.............. 1 6 RESTRICTED AREA 1 7
<OELETEOJ
...*...*...*...*...*...*...*...*...*...* * * * * *
- 1 7 SHUTDO't.'fl f~~~~ ~ ~..................................... * * * * * * * *
- 1 7
.............................................. 1 7 REPORTABLE EVENT SITE BOUNDARY SOURCE CHECK................................................ 1 7
................................................. 1 7 LH4ERICK UfJIT 2 Amendment fJo. ll, Hi
. ~
, 156 168
SECTION DEF INITIONS (Continued)
STAGGERED TEST BASI M
S.......................................... 1 8 THERMAL PO'i.JER TURBHJE BYPAS~. ~~~;~~~. ~~~~~~~~. ; ~ ~~~.................... * * * * * *
- 1 8
........................... 1 8 UN IDENTIFIED LEAKAGE.......................................... 1 8 UNRESTRICTED AREA II A
- 1 8 oENT ILnT ION EXHAUST TREATMENT SYSTEM
.............................. 1 9 Table 1. 2' Onerati ona1 C t'
l onditions....................................... 1 10 LIMERICK UNIT 2 Amendment No. 4B
SAFETY LIMITS AND LIMITINc
_o SAFETY SYSTEM SETTINGS SECTION
~ SAFETY LIMITS THER~1AL PO'*'ER L
O'vJ Pressure or Lm,* Flo*,
THER~1AL PO'*'ER H
- h
- * * * * * * * * * *
- 2 1 1gn Pressure and HigR Flow Reactor Cool ant: Svst em p
....... * * * * * * * * * * * * * * * ** 2 1 J
i::
m ress ure................................... 2 1 Reactor Vessel IJat:er Level........................................ 2 2 LIMITING SAFETY SYSTEM SETT IN GS Reactor Protection S yst:em Inst:rument:at:ion S et:poi nt:s............... 2 3 Table 2. 2. 1 1 R eact:or Protection System Inst:rument:at:ion Set:point:s..................... 2 4
~ SAFETY LH1ITS THER~1AL PO' 'ER n
' Lo*,; Pressure or Lo*, Flo*,
" * * * * * * * * * * * * * * * * * * * * * * * * *** 821 THER~1AL PO' 'ER n
' HigR Pressure and Higt:i Flow........................ 8 2 2 Int:ent:i ona l ly LeH Blank 8
Reaetoe GoolaAt System Peess*ee 2 4
................................... 8 2 5 Reactor Vessel IJat:er Level 8 2 5 LIMITING SAFETY SYSTEM SETT INGS Reactor Protection System Inst:rument:at:ion Set:point:s............... 8 2 6 LIMERICK UNIT 2
LIMIT I NG
~
ri
+NBH SURVEILLANCE REQUIREMENTS COND ITIONS FOR OPERAT ION AND REACTIVITY CONTROL SYSTEMS
............. 3/ 4 1 1 Y4.lc SHUTDOWN MARGIN *******...........................
314 1 1 3/ 4.1.1 Y"A N0~1 A L I ES..........................................,
3/ 4.1. 2 REACT IVIT n-3/ 4.1. 3 CONTROL RODS 3/ 4 1 3 Rod Operability ****************....................... 3/ 4 1 6 Rod Maximum Scram Insertion 1 7 Control
........ 3/ 4 t
- n Ti mes. * * * * * * * * * * *
- l Rod A.. erage Scram Inser i o
'~ 1 8 Centro-nv
. *. *. 31 ~
S m Insertion Times.............
Four Control Rod Groupcra
......... 3 1 ~ 1 9 d Scram Accumulators.......................
3/ 4 1 11 Control Ro Rod Dri ve Coupling ************
........................ 3 '4 1 13 Control Rod Dri ve Hous1 ng Figure 3.1. 5 2 CONTROL ROD PROGRAM CONTROLS 3/ 4 1 16 Rod Worth Minimizer.*****************
.............. ::::::::::: 3/ 4 1 18 Rod Block Monitor.********************................. 3/ 4 1 19 LIQUID cmHROL SYSTE~1................. :...........
STANDBY l t on Pentaborate So u l Figure 3.1. 5 1 i:!~::ature / Concentrati o ~............... 3/ 4 1 21 Requirements ********* ~ **
............ 3/ 4 1 22 (LEFT BLANK INTENTIONnLLY)..
3/ 4.1. 5 POWER DISTRIBUTION LIMITS 3/4 2 1 A HE AT GENERAT ION RATE....................
3/4.2.1 Al/ERA GE PLANAR LHlEnR n
h 3 '4 2 6a has been 3,'4 2 2 3 '4 1 1 t "
3 '4 1 1.......
Information on paf~~D ;refer to note on page 1
INTENTIONALLY OMI LIMERICK UNIT 2 Amendment
~lo
- 4
LIMITING COND ITIONS FOR OPERAT ION AND SURVEILLANCE REQUIREMENTS SECTION POWER DISTRIBUT ION LIMITS (Continued) 3/ 4.2.2 (DELETED)..................................................... 3/ 4 2 7 3/ 4.2.3 MINIMUM CRITICAL POWER RAT IO.................................. 3/ 4 2 8 Table 3.2.3 1 Deleted.
Information on pages 3/ 4 2 10 thru 3/4 2 11 has been INTENTIONALLY OM ITTED, refer to Note on page 3/ 4 2 10......... 3/ 4 2 10 3/ 4.2.4 LINEAR HEAT GENERATION RATE................................... 3/ 4 2 12 3/ 4.3 INSTRUMENTATION 3/ 4.3.1 REACTOR PROTECT ION SYSTEM INSTRUMENTAT ION..................... 3/ 4 3 1 Table 3.3.1 1 Reactor Protection System Instrumentation............................. 3/ 4 3 2 Table 3.3.1 2 Reactor Protection System Response Times.............................. 3/ 4 3 6 Table 4.3.1.1 1 Reactor Protection System Instrumentation Surveillance Requirements................................ 3/ 4 3 7 LIMERICK UN IT 2
Amendment No. 4, 48
LI MIT ING CO ND ITIO ~J S FOR OPERATimJ AND SlJRVEILLANCE REOlJIREME~JTS SECTION INSTRUMENTATION (Continued) 3/ 4.3.2 3/ 4.3.3 3/4.3.4 ISOLATION ACTUATION INSTRUMENTAT ION........................... 3/ 4 3 9 Table 3.3.2 1 Isolation Actuat i on Instrumentation...... 3/ 4 3 11 Table 3.3.2 2 Isolation Actuation Instrumentati on Setpoi nts................ 3/ 4 3 18 Table 3.3.2 3 Isolation System Instrumentation Response Ti me............................ 3/ 4 3 23 Table 4.3.2.1 1 Isolati on Actuati on Instrumentation Survei 11 ance Requirements.............. 3/ 4 3 27 EMERGENCY CORE COOL ING SYSTEM ACTUAT ION HJSTRUME ~JTATimJ............................................... 3/ 4 3 32 Table 3.3.3 1 Emer§enC:J' Core Cool in§ S:ystem Actuati on Instrumentati on................ 3/ 4 3 33 Table 3.3.3 2 Emer§enC:J' Core Cool in§ S:ystem Actuation Instrumentation Setpoints...... 3 / ~ 3 37 Table 3.3.3 3 Emer§ency Core Coolin§ Syst em Response Times........................... 3 / ~ 3 39 Table 4.3.3.1 1 Emer§ency Core Coolin§ System Actuati on Instrumentati on Survei 11 ance Requirements.............. 3/4 3 40 REC IRCULATION PUMP TRIP ACTUAT ION IN STRUMENTAT ION ATWS Rec i rcu l ation Pump Trip System Instrumentation........... 3/4 3 42 Table 3.3.4.1 1 ATWS Rec i rcu l ation Pump Trip System Instrumentation................. 3/4 3 43 Table 3.3.4.1 2 ATWS Rec i rcu l ation Pump Trip System Instrumentat i on Set points.............................. 3/4 3 44 Table 4.3.4.1 1 (Deleted).............................. 3/4 3 45 End of Cycl e Rec i rcu l ati on Pump Trip System Instrumentati on............................................... 3/4 3 46 LIMERICK UNI T 2 Amendment No. 147
LIMITING COND ITIONS FOR OPERAT ION AND SURVEILLANCE REQUIREMENTS SECTION INSTRUMENTATION (Continued) 3 / ~
. 3
. 5 Table 3.3.4.2 1 End of Cycle Recirculation Pump Trip System Instrumentation............ 3/4 3 48 Table 3.3.4.2 2 End of Cycle Recirculation Pump Trip Setpoints......................... 3/4 3 49 Table 3.3.4.2 3 End Of Cycle Recirculation Pump Trip System Response Time.............. 3/ 4 3 50 Table 4.3.4.2.1 1 (Deleted)............................ 3/ 4 3 51 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION HlS T RUME~H A Ti mL.............................................. 3 1 ~ 3 52 Table 3.3.5 1 React or Core Isolation Cooling System Actuation Instrumentation......... 3 / ~ 3 53 Table 3.3.5 2 Reactor Core Isolation Cooling System Actuation Instrumentation Set points................................ 3/ 4 3 55 Table 4.3.5.1 1 (Deleted).............................. 3/ 4 3 56 3/4.3.6 CONTROL ROD BLOCK INSTRUMENTAT ION............................. 3/4 3 57 Table 3.3.6 1 Control Rod Block Instrumentation........ 3/4 3 58 Table 3.3.6 2 Control Rod Block Instrumentation Setpoi nts................................ 3/4 3 60 Figure 3.3.6 1 SRM Count Rate Versus Signal to Noise Ratio.................... 3/4 3 60b Table 4.3.6 1 Control Rod Block Instrumentation Survei 11 ance Requirements................ 3/4 3 61 3/4.3.7 MON ITORING INSTRUMENTATION Radiation Monitoring Instrumentation.......................... 3/4 3 63 Table 3.3.7.1 1 Radiation Monitoring Instrumentation........................ 3/4 3 64 LIMERICK UNIT 2 Amendment No. ~
. 147
LIMITING COND ITIONS FOR OPERAT ION AND SURVEILLANCE REQUIREMENTS SECTION 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 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 (Del eted)........................... 3/4 3 83 Accident Monitoring Instrumentation......................... 3/4 3 84 Table 3.3.7.5 1 Accident Monitoring Instrumen tati on.............................. 3/4 3 85 Table 4.3.7.5 1 Accident Monitoring Instrumenta ti on Survei 11 ance Requirements...... 3/4 3 87 Source Range Monitors
................................... 3/4 3 88 The information from page 3/4 3 89 has been intentionally omitted.
Refer to note on page
................................... 3/4 3 89 Chlorine Detection System................................... 3/4 3 90 To>d c Gas Detection System.................................. 3/4 3 91 DELETED; Refer to note on page.............................. 3/4 3 92 LIMERICK UNIT 2 Amendment
~lo
. 11, 313, ~
, 79, 147
LIMITING COND ITIONS FOR OPERAT ION AND SURVEILLANCE REQUIREMENTS SECTION
.flAbf INSTRUMENTATION (Continued)
(Deleted)........................................................ 3/ 4 3 97 The information from pages 3/ 4 3 98 through 3/ 4 3 101 has been intentional ly omitted.
Refer to note on page 3/4 3 98......................... 3/ 4 3 98 The information from pages 3/ 4 3 103 through 3/ 4 3 108 has been intentional ly omitted.
Refer to note on page 3/4 3 103........................ 3/ 4 3 103 3/ 4.3.8 (Deleted)
The information on pages 3/ 4 3 110 and 3/ 4 3 111 has been intentionally omitted.
Refer to note on page 3/ 4 3 110...................... 3/ 4 3 110 3/ 4.3.9 FEEDWATER/ MAIN TURB INE TRIP SYSTEM ACTUATION HJSTRUMENTATION........................................... 3/ 4 3 112 Table 3.3.9 1 Table 3.3.9 2 Table 4.3.9.1 1 Feedwater/ Main Turbine Trip System Actuation Instrumentation............... 3/ 4 3 113 Feedwater/ Main Turbine Trip System Actuation Instrumen tati on Set points............................... 3/ 4 3 114 (Deleted)...................................... 3/ 4 3 115 Y-4-:-4 REACTOR COOLMH SYSTEM 3/ 4.4.1 REC IRCULATION SYSTEM Reci rcul ati on Loops.............................................. 3/ 4 4 1 LIMERICK UN IT 2 Amendment No. 11, e4, 92, 117, 10, 191
LIMITING CON DI TIONS FOR OPERAT ION AND SURVE I LLANCE REQU IREMENTS SECTION REACTOR COOLANT SYSTEM (Conti nued)
Figure 3.4.1. 1 1 Del eted............................... 3/ 4 4 3 Jet Pumps..................................................... 3/ 4 4 4 Reci rcul at i on Pumps........................................... 3/ 4 4 5 Idl e Rec i rcu l ati on Loop St artup............................... 3/ 4 4 6 3/ 4.4.2 SAFETY/RELIEF VALVES.......................................... 3/ 4 4 7 3/ 4.4.3 REACTOR COO LANT SYSTEM LEAKAGE Leakage Detecti on Systems..................................... 3/ 4 8
Operationa l Leakage........................................... 3/ 4 9
Table 3.4.3.2 1 Del eted................................ 3/ 4 4 11 3/ 4.4.4 (Deleted) The information from pages 3/ 4 4 12 throug h 3/ 4 4 14 has been i ntentional ly omitted.
Refer to note on page 3/ 4 4 12............................... 3/ 4 4 12 3/ 4.4.5 SPECIFIC ACTIVITY............................................. 3/ 4 4 15 3/ 4.4.6 Table 4.4.5 1 Primary Coolant Specific Activity Sampl e and Ana lysis Program.............. 3/ 4 4 17 PRESSURE/TEMPERATURE LIMITS Reactor Cool ant System........................................ 3/ 4 4 18 Figure 3.4.6.1 1 Mi ni mum Reactor Pressure Vessel Metal Temperature Vs. Reactor Vessel Pressure....................... 3/ 4 4 20 Table 4.4.6.1. 3 1 Del eted.............................. 3/ 4 4 21 Reactor Steam Dome............................................ 3/ 4 4 22 3/ 4.4.7 MA IN STEAM LINE ISOLATION VALV ES.............................. 3/ 4 4 23 3/ 4.4.8 (DELET ED )..................................................... 3/ 4 4 24 LIM ERICK UNI T 2 Amendment No.
l ~ G
, l ~ i
, 1 ~9
, 144
, 160
+NBH LIMITING COND ITIONS FOR OPERAT ION AND SURVEILLANCE REQUIREMENTS SECTION REACTOR COOLANT SYSTEM (Continued) 3/ 4.4.9 RES IDUAL HEAT REMOVAL Hot Shutdo*,.*n............................................... 3/ 4 4 25 Cold Shutdo*vm.............................................. 3/ 4 4 26 Y-4-: EMERGrnCY CORE COOLHJG SYSTEMS 3/ 4.5.1 EGGS OPERATHJG........................................... 3/ 4 5 1 3/ 4. 5. 2 EGGS SHUTDOIHJ............................................ 3/ 4 5 6 3/ 4. 5. 3 SUPPRESSIO~J CHAMBER........................................ 3/ 4 5 8 Y-4-: CONTAHJME~JT SYSTEMS 3/ 4.6.1 PRIMARY CONTAINMENT Primary Containment Integrity.............................. 3/ 4 6 1 Primary Containment Leakage................................ 3/ 4 6 2 Primary Containment Air Lock............................... 3/ 4 6 5 MSIV Leakage Alternate Drain Pathway....................... 3/ 4 6 7 Primary Containment Structural Integrity................... 3/ 4 6 8 Dry,.*ell and Suppression Chamber Internal Pressure.......... 3 / ~ 6 9 Dry,.*el l Average Air Temperature............................ 3 / ~ 6 10 Drywell and Suppression Chamber Purge System............... 3/ 4 6 11 3/ 4.6.2 DEPRESSURIZATION SYSTEMS Suppression Chamber........................................ 3/ 4 6 12 Suppression Pool Spray..................................... 3/ 4 6 15 Suppression Pool Cooling................................... 3/ 4 6 16 3/ 4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES....................... 3/ 4 6 17 LIMERICK UNIT 2 Amendment No. 53, 107
LIMITING COND ITIONS FOR OPERAT ION AND SURVEILLANCE REQUIREMENTS SECTION CONTA INMENT SYSTEMS (Conti nued) 3/4.6.4 VACUU~~ RELi EF Suppression Chamber Dry'vi'el l Vacuum Breakers..................... 3/4 6 44 3/4.6.5 SECONDARY CONTA INMENT Reactor Enclosure Secondary Containment Integrity................. 3/ 4 6 46 Refueling Area Secondary Containment Integrity.................... 3/ 4 6 47 Reactor Enclosure Secondary Containment Automatic I sol ati on Val ves.................................................. 3 / ~ 6 ~8 Refueling Area Secondary Containment Automatic I sol ati on Val ves.................................................. 3 / ~ 6 50 Standby Gas Treatment System Common System...................... 3/ 4 6 52 Reactor Enclosure Recirculation System............................ 3/ 4 6 55 3/4.6.6 PRIMARY CONTA INMENT ATMOSPHERE CONTROL Deleted........................................................... 3/ 4 6 57 Drywell Hydrogen Mi xing System.................................... 3/ 4 6 58 Drywell and Suppression Chamber Oxygen Concentration.............. 3/ 4 6 59 3/ 4.7 PLANT SYSTEMS 3/ 4.7.1 SERVICE WATER SYSTEMS Residual Heat Remova l Service IJater System Common System............................................................ 3/ 4 7 1 Emergency Service Water System Common System.................... 3/ 4 7 3 Ultimate Heat Sink................................................ 3/ 4 7 5 LIMERICK UN IT 2 Amendment No. ~
, 135
LI MI TI NG COND I TI ONS FOR OPERAT I ON AND SURVEILLANCE REQUIREMENTS SECTION PLANT SYSTEMS (Contin ued) 3/ 4. 7. 2 CONTROL ROOM EMERGENCY FRESH AI R SUPPLY SYSTEM COMMON SYSTE~1........................................................ 3/ 4 7 6 3/ 4. 7. 3 REACTOR CORE I SOLAT I ON COOLING SYSTEM......................... 3/ 4 7 9 3/ 4. 7. 4 S~JUBBERS...................................................... 3/ 4 7 11 Figure 4. 7.4 1 Sampl e Pl an 2) For Snubber Functional Test........................... 3/ 4 7 16 3/ 4. 7. 5 SEALED SOURCE cmnAMHJATimJ................................... 3/ 4 7 17 3 1 ~
. 7. 6 DELETED; Refer to note on page................................ 3 1 ~ 7 19 3 1 ~
. 7. 7 DELETED; Refer to note on page................................ 3 1 ~ 7 19 3/ 4. 7.8
~1AHJ TURB I NE BYPASS SYSTEM.................................... 3/ 4 7 33 Y-4-: ELECTRI CAL POl.'ER SYSTEMS 3/ 4.8. 1 A. G. SOURCES A. C. Sources Operating................................... 3/ 4 8 1 Table 4.8. 1.1. 2 1 DELETED................................. 3/ 4 8 8 A. C. Sources Shutdo*,m.................................... 3/ 4 8 9 3/ 4.8. 2 D. C. SOURCES D. C. Sources Operating................................... 3/ 4 8 10 LI MERI CK UN I T 2 Amendment
~J o
. le, ~
, 150
LIMITING COND ITIONS FOR OPERAT ION AND SECTION SURVEILLANCE R EOU IREME~HS ELECTRICAL p 3/ 4.8.3 3 / ~
. 8
. ~
OIJER SYSTEMS ( c ont1nued)
Table 4.8.2. 1 1 Battery Survei l lan Requirements cc D.C. Sources Shutdmm
- * * * * * * * *
- 3/ 4 8 13 U01
~'t;'
J SrtI +T E-E -flPBJOI w.tJ E~Rt-&.
D I~Srt:
T-R-R II-EBl-t!Uf-TH Iom~J-&\\f..q..Q
.. '1.£. * * * * * * * * * * * * * * * * * * * * * * * * * *
-~- r SYSTEMS
- 3/ 4 8 14 Distribution Operating........
D
. t is ribution Shutdown
- * * * * * * * * * *
- 3/ 4 8 15 ELECTRICAL E8UIPMEMT
- ri - r1-PROT
.... * * * * * *
- 3/ 4 8 18 ECTIVE DEVICES (Deleted).................................................. 3 / ~ 8 21 (Deleted)........................................
S~ stem Elect r ic
.......... 3 1 ~ 8 2' Pm,*er Monitoring
...... 3/ 4 8 28 Reactor Protect
- lOn
-3+4-: REFUELHJG OPERATimJS 3/ 4.9.1 3/ 4.9.2 3/ 4.9.3 3/ 4.9.4 3/ 4.9.5 3/ 4.9.6 3 / ~
. 9
. 7 LH4ERICK REACTOR MODE SW ITCH
................................ 3/ 4 9 1 INSTRUMENTATION............................................ 3/ 4 9 3 CONTROL ROD POS ITION..........
............................... 3/ 4 9 7 REFUELING PLATFORM
................................ 3/ 4 9 8 CRMJE TR A\\'EL M V SPENT FUEL STORAGE POOL......... * * *
- 3 I
........ d 9 10 "ATE "n R LEVEL 3
/ 4 9 12 SPENT FUEL STORAGE POOL
............. 3 / ~ 9 11 REACTOR VESSEL...
"'ATER i\\11 LEVEL U~JIT 2 Amendment No. 57 170
LIMITING COND ITIONS FOR OPERAT ION AND SURVEILLANCE REQUIREMENTS SECTION REFUELING OPERATIONS (Continued )
3/4.9.10 CONTROL ROD REMOVAL Single Control Rod Removal................................. 3/4 9 13 Multiple Control Rod Removal............................... 3/4 9 15 3/ 4.9. 11 RES IDUAL HEAT REMOVAL AND COOLANT CIRCULAT ION High IJater Level........................................... 3/ 4 9 17 Lo*,, \\Jater Level............................................ 3/ 4 9 18 3/ 4.10 SPEC IAL TEST EXCEPT IONS 3/ 4.10.1 PRIMARY CONTA INMENT INTEGRITY.............................. 3/ 4 10 1 3/ 4.10.2 ROD \\.'ORTH MHWH ZER........................................ 3/ 4 10 2 3/ 4.10.3 SHUTDOWN MARG IN DEMONSTRAT IONS............................. 3/ 4 10 3 3/ 4.10.4 RECIRCULATimJ LOOPS........................................ 3/ 4 10 4 3/ 4.10.5 OXYGEN CONCENTRAT ION....................................... 3/ 4 10 5 3/ 4.10.6 TRAHJ me STARTUPS.......................................... 3/ 4 10 6 3/ 4.10.7 SPECIAL INSTRUMENTATION INITIAL CORE LOADING............. 3/ 4 10 7 3/ 4.10.8 INSERVICE LEAK AND HYDROSTATIC TESTING..................... 3/ 4 10 9 3/ 4. 11 RADIOACT IVE EFFLUENTS 3/ 4.11.1 3/ 4.11.2 LIQUID EFFLUENTS The information from pages 3/ 4 11 1 through 3/ 4 11 6 has been intentionally omitted.
Refer to note on page 3/4 11 1................... 3/ 4 11 1 Liquid Holdup Tan ks........................................ 3/ 4 11 7 GASEOUS EFFLUENTS The information from pages 3/ 4 11 8 through 3/ 4 11 14 has been intentionall y omitted.
Refer to note on page 3/ 4 11 8................... 3/ 4 11 8 LIMERICK UN IT 2 Amendment No. 11, 95
LIMITING COND ITIONS FOR OPERAT ION AND SURVEILLANCE REQUIREMENTS SECTION RAD IOACTIVE EFFLUENTS (Contin ued)
The information from page 3/ 4 11 15 has been intentionally omitted.
Refer to note on page 3/4 11 15.............................. 3/ 4 11 15 Main Condenser............................................... 3/ 4 11 16 The information on page 3/4 11 17 has been intentional ly omitted.
Refer to note on this
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................................................... 3/ 4 11 17 3/ 4. 11. 3 (Deleted) The information on pages 3/ 4 11 18 through 3/ 4 11 20 has been intentionall y omitted.
Refer to note on page 3/ 4 11 18.
3/ 4. 11. 4 (Deleted)
................................................... 3/ 4 11 18 3/ 4. 12 (Deleted) The information on pages 3/4 12 1 through 3/4 12 14 has been intentionally omitted.
Refer to note on page 3/4 12 1..................... 3/ 4 12 1 LIMERICK UN IT 2 Amendment No. 11, 191
SECTION 3/ 4. 0 APPLICABI LIT¥..................................................... B 3/ 4 0 1 3/ 4.1 REACT IVITY CONTROL SYSTEMS 3/ 4.1. 1 SHUTDO'.*m ~MRGIN.............................................. B 3/ 4 1 1 3/ 4.1. 2 REACTIVITY ANOMALIES......................................... B 3/ 4 1 1 3/ 4.1. 3 cmnROL RODS................................................. B 3/ 4 1 2 3/ 4.1. 4 cmnROL ROD PROGRAM cmnROLS................................. B 3/ 4 1 3 3/ 4.1.5 STANDBY LIQUID CONTROL SYSTEM................................ B 3/ 4 1 4 3/ 4.2 POWER DISTRIBUT ION LIMITS 3/ 4.2.1 AVERAGE PLANAR LINEAR HEAT GENERAT ION RATE......................................................... B 3/ 4 2 1 3/ 4.2.2 (DELETED).................................................... B 3/ 4 2 2 LEFT HJTENTimJALLY BLMJK................................................ B 3/ 4 2 3 3/ 4. 2. 3 MHW1UM CRITICAL POIJER RATIO................................. B 3/ 4 2 4 3/ 4.2.4 LINEAR HEAT GENERAT ION RATE.................................. B 3/ 4 2 5 Y-4-: rn STRUM E
~JTATI mi 3/ 4.3.1 REACTOR PROTECT ION SYSTEM INSTRUMENTAT ION.................... B 3/ 4 3 1 3/ 4.3.2 ISOLATION ACTUATION INSTRUMENTAT ION.......................... B 3/ 4 3 2 3/ 4.3.3 EMERGENCY CORE COOL ING SYSTEM ACTUAT ION HJSTRUME~JTATimJ.............................................. B 3/ 4 3 2 3/ 4.3.4 REC IRCULATION PUMP TRIP ACTUAT ION INSTRUMENTAT ION............ B 3/ 4 3 3 3/ 4.3.5 REACTOR CORE ISOLAT ION COOL ING SYSTEM ACTUAT ION HJSTRUME~JTATimJ.............................................. B 3/ 4 3 4 3 / ~
. 3. 6 cmnROL ROD BLOCK HJS T RU~1E~JTATION............................ B 3 / ~ 3 ~
3 / ~
. 3
. 7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation......................... B 3/ 4 3 5 LIMERICK UN IT 2 Amendment No. 4, 32, 48
SECTION 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 ~4onitors...................................... B 3/ 4 3 5 (Deleted).................................................. B 3/ 4 3 6 Chlorine and TOJ(i c Gas Detection Systems................... B 3/ 4 3 6 (Deleted).................................................. B 3/ 4 3 6 (Deleted).................................................. B 3/ 4 3 7 (Deleted).................................................. B 3/ 4 3 7 (Deleted).................................................. B 3/ 4 3 7 3/ 4.3.8 (Deleted).................................................. B 3/ 4 3 7 3/ 4.3.9 FEEDIJATER/f4AIN TURBINE TRIP SYSTEM ACTUATimJ INSTRUME~HATimJ............................................ B 3/ 4 3 7 Bases Figure B 3/ 4. 3 1 Reactor Vessel Water Le vel........................ B 3/ 4 3 8 3/ 4. 4 REACTOR COOLANT SYSTEM 3/ 4. 4. 1 RECIRCULATimJ SYSTEM....................................... B 3/ 4 4 1 3/ 4. 4. 2 SAFETY / RELi EF VALVES....................................... B 3/ 4 4 2 3/ 4. 4. 3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems.................................. B 3/ 4 4 3 Opera ti on al Leakage........................................ B 3/ 4 4 3 3/ 4. 4. 4 CHEMISTRY.................................................. B 3/ 4 4 3a LIMERICK UNIT 2 Amendment No. 11, 12, 17, 32, e, ~
. 79, 92, 117, 191
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SECTION REACTOR COOLANT SYSTEM (Continued )
3/4.4. 5 3/4.4. 6 SPECIFIC ACTIVITY PRESSURE / TEMPERAT~~~ * ~~~ ~ ;~ *.................................. B 3/4 4 4 Bases Table B 3/4.4. 6 *1**********************************
B 3/4 4 4 Reactor Vessel Bases Figure B 3/ 4.4. 6 1 Toughness......... * * * * * * * * * * * *
- B 3/4 4 7 Fast Neutron Fluence (E>l ~eV) At 1/ 4 T As A Function of Service Life 3 I ~
- * * * * * * * * * * * * ** * * * * * * * * * * *
- B 3/ 4 4 8 r
. ~
. 7 MAIN STEAM LINE ISOLATION VALVES 18ELETED )
- * * * * * * * * * * * * ** * * * * * * * * * * * * * *
- B 3f 4 4 6 3 ' 4 4 9 B 3 / ~
~ 6 r
RES IDUAL HEAT REMOVAL Y-4-: EMERGE~lCY CORE COOLHJG S;~;~~~~................................... B 3/4 4 6 3 / ~
. ~
. 8 3/ 4. 5. 1 and 3/ 4. 5. 2 EGGS OPERAT ING and SHUTDOWN Y-4-: CONTAHJME ~H SYSTEMS
............................ * * * * * * * *
- B 3/ 4 5 4 3/ 4. 6. 1 PRIMARY CONTA INMENT Primary Containment Integrity................. * * * * * * * * *
- B 3/ 4 6 1 Primary Containment Leakage
. *. *. *. *. *. *. *. *. *. * * * * * * * * *
- B 3/ 4 6 1 Primary Genta
- t inmen Structural Integrity..........
.............................................. B 3 / ~ 6 2 Dry*,.*el l A"era A*
N V ge nir Temperature......................... B 3 11 ~ 6 2 Dry*1vel l d s anuppress ion Chamber Purge 3/4. 6. 2
................... * * * * * * * * * * * *
- B 3/4 6 3 LIMERICK UN IT 2 Amendment No. l§Q Associated. *i th A d
n nmen ment 178
SECTION CONTA I NMENT SYSTEMS (Cont i nued) 3/4.6.3 PRIMARY CONTA I NMENT ISOLAT I ON VALVES................. B 3/4 6 4 3/4.6.4 VACUU~4 RELi EF........................................ B 3/4 6 4 3/4.6. 5 SECON DARY CONTA I NME~JT................................ B 3/4 6 5 3/ 4.6.6 PRIMARY CONTA I NMENT ATMOSPHERE CONTROL. *. *. *. *. *. *. *. B 3/ 4 6 6 Y-4-:-f.
PLMJT SYSTrnS 3/ 4. 7. 1 SERVICE l.'ATER SYSTEMS COMMON SYSTrnS............... B 3/ 4 7 1 3i'4. 7. 2 CO~JTROL R00~4 E~4ERGE~JCY FRESH AIR SUPPLY SYSTE~4 cm4MmJ SYSTrn........................................ B 3/ 4 7 1 3/ 4. 7.3 REACTOR CORE I SOLATimJ COOLING SYSTEM................ B 3/ 4 7 le 3/ 4. 7.4 SNUBBERS............................................. B 3/ 4 7 2 3/ 4. 7. 5 SEALED SOURCE CON TAM I ~JAT I mJ.......................... B 3/ 4 7 3 3 / ~
. 7
. 6 (Deleted)............................................ B 3 / ~ 7 3 / ~
. 7
. 7 (Deleted)............................................ B 3 / ~ 7 3 / ~
. 7
. 8 MAI ~J TURB HJ E BYPASS SYSTEM........................... B 3 / ~ 7 5 Y-4-: ELECTR I CAL POl.'ER SYSTrn 3/ 4.8. 1, 3/ 4.8.2, and 3/ 4.8.3 A. G. SOURCES, D. C. SOURCES, AND ONS I TE POWER DISTRIBUTimJ SYSTE~4S. *. *. *. *. *. *. *. *. *. *. *. **. *. *. *. *. *.
- B 3/ 4 8 1 3/ 4.8.4 ELECTRICAL EQUIPMENT PROTECT I VE DEVICES *. *. *. *. *. *. *. B 3/ 4 8 3 Y-4-: RE FUELHJG OPERATimJS 3/ 4.9. 1 REACTOR ~40DE S\\JITCH *. *. *. *. *. *. *. *. *. *. *. *. **. *. *. *.
- B 3/ 4 9 1 3/ 4.9.2 HJSTRU~4E~JTATimJ *. *. *. *. *. *. *. *. *. *. *. *. *.. *. *. *. *. *.
- B 3/ 4 9 1 3/ 4.9.3 cmJTROL ROD POSITIO~J. *. *. *. *. *. *. *. *. *. *. *. **. *. *. *.
- B 3/ 4 9 1 3/ 4.9.4 DECAY TH4E. *. *. *. *. *. *. *. *. *. *. *.. *. *. *. *. *. *. *. *. *.
- B 3/ 4 9 1 3/ 4.9. 5 cm4MU~HCATimJS. *. *. *. *. *. *. *. *. *. *. *.. *. *. *. *. *. *. *.
- B 3/ 4 9 1 LI MERI CK UN I T 2 Afflendfflent
~Jo
. le, ~
, 149
SECTION REFUELING OPERATIONS (Cont i nued )
3/4. 9. 6 REFUELHJG PLATFORM......................................... B 3/4 9 2 3/4. 9. 7 CRANE TRAVEL SPENT FUEL STORAGE POOL..................... B 3/4 9 2 3/4.9.8 and 3/4.9.9 WATER LEVEL REACTOR VESSEL AND 'tJATER LEVEL SPE~JT FUEL STORAGE POOL.................. B 3/4 9 2 3/ 4.9. 10 cmnROL ROD REMOVAL........................................ B 3/ 4 9 2 3/ 4.9. 11 RES IDUAL HEAT REMOVAL AND COOLANT CIRCULAT ION.............. B 3/ 4 9 2 3/ 4. 10 SPEC IAL TEST EXCEPTIONS 3/ 4. 10.1 PRIMARY cmHAHJMENT HJTEGRITY.............................. B 3/ 4 10 1 3/ 4. 10. 2 ROD \\.'ORTH
~4HJIMIZER........................................ B 3/ 4 10 1 3/ 4. 10. 3 SHUTDO\\m MARG HJ DEMmJSTRATimJS............................. B 3/ 4 10 1 3/ 4. 10. 4 REC IRCU LAH mJ LOOPS........................................ B 3/ 4 10 1 3/ 4. 10.5 OXYGEN CONCENTRAT ION....................................... B 3/ 4 10 1 3/ 4. 10.6 TRAHJHJG STARTUPS.......................................... B 3/ 4 10 1 3/ 4. 10. 7 SPEC IAL HJSTRUME~JT ATim J HJITIAL CORE LOADHJG............. B 3/ 4 10 1 3/ 4. 10.8 INSERV ICE LEAK AND HYDROSTATIC TESTING..................... B 3/ 4 10 2 3/ 4. 11 RAD IOACTIVE EFFLUENTS 3/ 4. 11. l LIQU ID EFFLUENTS The i nformati on on page B 3/ 4 11 1 has been i ntentiona l ly omitted.
Refer to note on thi s page....................................................... B 3/ 4 11 1 (Deleted).................................................. B 3/ 4 11 2 Liqui d Holdup Tan ks........................................ B 3/ 4 11 2 3/ 4. 11. 2 GASEOUS EFFLUE ~JTS (Deleted).................................................. B 3/ 4 11 2 The information on page B 3/ 4 11 3 has been intentiona l ly omitted.
Refer to note on this page....................................................... B 3/4 11 3 (Deleted).................................................. B 3/4 11 4 LIMERICK UNI T 2 Amendment No. 11, 95
SECTION RADIOACTIVE EFFLUENTS (Contin ued)
(Deleted) The information from page B 3/4 11 4 has been intentionall y omitted.
Refer to note on page B 3/4 11 4............. B Main Condenser.......................................... B (Deleted)............................................... B 3/ 4. 11.3 (Deleted)............................................... B 3/ 4. 11.4 (Deleted)............................................... B 3/ 4. 12 (Deleted) The information from pages B 3/ 4 12 1 through B 3/ 4 12 2 has been intentionally omitted.
Refer to note on page 3/4 11 4 3/4 11 5 3/ 4 11 5 3/ 4 11 5 3/ 4 11 5 B 3/ 4 12 1................................... B 3/ 4 12 1 LIMERICK UNIT 2 Amendment No. 11, 191
SECTION :-+/--
-s+ff E>(Cl us i on Area F i gu~~ * ~~ ~ ~ ~ * ~ *.. E........................................ *
)(Cl usi on Area 5 1 5 2 Low Popul ation Zone................................................ 5 1 Figure 5. 1.2 1 L
tBO~~J~P~o~p~u+
l ~a~tiH
- o*nt-ZZBo~ne e-:-:-:-:-:-:--;-;-~,.-;-:--;-:--;-:-:-:-:....,..-_i;;._2 Ma~s Defi Ai A§ UNRESTRIGT
- 5 3 for Radioacti ve Ga ED n R~ n S and SITE BOUN DARY seous and Liqui d Effl uents Figure 5.1.3 la Ma D f..
Radioacti ve Gasco pc i_ni ng U~JRESTR I CT ED ' RE ' S us and Liquid Effl uents n
n for 5 1
<Del ete6)
"" *" "........ 5 5
. ~;~ * ~;~~;~ * ~; * ~:~~ * ; * ~ * ;:~ * ~~~;.......................... 5 1 omitted.
Refer to note on intentiona l ly page 5 6...................... : CONTAHJ~1 E ~H 5 6 Fi §"e 5. 1. 3 lB M
................. 5 ~
Radioacti ve Gase ap Defi_ni n_g U~JRESTR I CT ED ' RE ous and Liquid Effl uents n
AS for Configurati on Design Temper~~~;~ * ~n* d*.P................ *. * * * * * * * * * * * * * * * * * * * * * * * * *.. 5 1 res sure Seceedary Ge eta 1 Ame Rt
.......... " " " " ".. * " ".......... 5 1 5
- 3 REACTOR CORE
.................................... * * * * * * * * * *
- 5 7 Fuel Assembl ies Control Rod Ass~~~ l* i* ~~................... * * * * * * * * * * * * * * * * * * * * * * *
- 5 7 :-4 REACTOR COOLMH SYSTE ~;............................................. 5 7 Design Pressure and Temperature Vol ume
....... * * * * * * * * * * * * * * * * * * * * * * * * * * *... 5 7 FUEL ~;~~;~~........................................... * * * * * * * * * * *. 5 8 Cri t i cal i ty......................................................... 5 8 LIMERICK UNI T 2 Amendment No. 11
SECTION FUEL OR Ar E E Cont i nued)
...... 5 8 ST no LIMIT.. **********
COMPONENT CYCL IC OR TRANS IENT L'mits.......... 5 9 t Cycl ic or Transient i Table 5.6.1 1 Componen LIMERICK UN IT 2
ADM INISTRATIVE cmnRoLs M
SECTION RES PONSIBILITY ****.......
........ * * * * * * *..... :-+/--
6 I
.. 6 1 6 1 ORGANIZATION.............
~
' ND ONSITE ORGAN IZATION..........
............ 6 3
- 6. 2. 1 OFFSITE n 1 I DELETED................
6 2 Figure 6. 2.
DELETED............................
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- 6. 2.3 DELETED;
- 6. 2. 4 SHIFT T ECH~HCA M
i L ADllISOR...................
. 6 6 ST AFF QUALI FICAT IONS..............
.............. 6 7 :-3 u ~H T M
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Deleted Deleted * * * * * *
- LH4ER ICK Deleted * * * * * * * * * * *
- 6 7 6 8 Deleted........
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............... 6 9
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ADM I NI STRAT I VE CONTROLS SECTION :-5-: Deleted Deleted.................................................... 6 9 Deleted.................................................... 6 9 Deleted Deleted.................................................... 6 10 Deleted.................................................... 6 10 Deleted.................................................... 6 10
.................................................... 6 10 Deleted.................................................... 6 10 Deleted.................................................... 6 12 Deleted
.fr::j-SAFETY LIMIT VIOLATION................................... * * * * * * * * *
- 6 12a REPORTABLE EVE~J; * ;~;;~~:.................................. * * * * * * * * *
- 6 12 :-8 PROCEDURES MJD PROGR' MS............................................ 6 12a M
- * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- 6
- ..,.<)
RE PORT! NG REQU !REM EN TS 13
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ROUTINE REPORTS............................................ 6 15 Startup Report.....
6 Moot Al Y O~e rati "§ Re~o rts 15
.................................. 6 16 Anrwal Rad1olo.,,
- l
- i"'l ca EAvi rOAITleAtal Opera ti A§ Report......... 6 16 AAAual Radioactive EfflueAt Release Report................. 6 17 CORE OPERATING LIMITS REPORTS * * * * * * * * * * * * * * * * * * * * * * * * * * * *.. 6 18a :-1 DELETED
................................. * * * * * * * * * *
- 6 18a
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RAD I ATI~~: * ~~~;~~; ; ~~: * ~~~~~~~~............................ * * * * * * * * *
- 6 19 :-1 HI GH RADIATimJ ' RE '
............................. * * * * * * * *
- 6 20 H
H * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- 6 20 SPECIAL REPORTS LI MERI CK UN I T 2
ADMINI STRAT I VE CONTROLS SECTION :-H-PROCESS CONTROL PROGRAM EPCP)
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OFFSITE DOSE CALCULATION MA NU~~. ;~ ~~ ~: ; *...*...*...*..*...*...*...* 6 21
- 6. JS ED el eteS I
. * * * * * * * * * * * * * * * * * * * * * * * * * *
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- 6 22
'6-:-+/- SAFETY F U~J CTimJ DETER~1HJATimJ
........................ 6 22 PROGRAM ESFDP)...................... 6 23 LI MERI CK UNI T 2
)()(V i i i Amendment No. 11, 14 9, 181
ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.8 Nine Mile Point Nuclear Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-63 and NPF-69 Revised Technical Specification Pages Nine Mile Point Unit 1 ii iii iv v
vi Nine Mile Point Unit 2 ii iii iv
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TABLE OF CONTENTS
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3.3.1.1 3.3.1.2 3.3.2.1 3.3.2.2 3.3.3.1 3.3.3.2 3.3.4.1 3.3.4.2 3.3.5.1 3.3.5.2 3.3.5.3 USE ANO APPLICATION Definitions........................................................................................ 1.1 1 Logical Connectors.......................................................................... 1.2 1 Completion Times............................................................................ 1.3 1 Frequency........................................................................................ 1.4 1 SAFETY LIMITS (Sbs)
Sbs.................................................................................................. 2.0 1 Sb \\'iolations.................................................................................... 2.0 1 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY......... 3.0 1 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY........................ 3.0 5 REACTIVITY CONTROL SYSTEMS SHUTOOVVN MARGIN (SOM)..................................................... 3.1.1 1 Reactivity Anomalies................................................................... 3.1.2 1 Control Rod OPERABILITY......................................................... 3.1.3 1 Control Rod Scram Times............................................................ 3.1.4 1 Control Rod Scram Accumulators................................................ 3.1.5 1 Rod Pattern Control..................................................................... 3.1.6 1 Standby Liquid Control (SLC) System.......................................... 3.1.7 1 Scram Discharge Volume (SO\\/) \\/lnt and Drain Valves....................................................................... 3.1.S 1 POWER DISTRIBUTION LIMITS AVERA.GE PLANAR LINEAR HEAT GENERATION RA.TE
(.A.PLHGR).......................................................................... 3.2.1 1 MINIMUM CRITICAL POWER RATIO (MCPR)............................ 3.2.2 1 LINEAR HEAT GENERATION RATE (LHGR).............................. 3.2.3 1 INSTRUMENTATION Reactor Protection System (RPS)
Instrumentation................................................................... 3.3.1.1 1 Source Range Monitor (SRM) Instrumentation............................ 3.3.1.2 1 Control Rod Block Instrumentation.............................................. 3.3.2.1 1 Feedwater System and Main Turbine High 'Nater Level Trip Instrumentation.................................................. 3.3.2.2 1 Post Accident Monitoring (PAM) Instrumentation......................... 3.3.3.1 1 Remote Shutdown System.......................................................... 3.3.3.2 1 End of Cycle Recirculation Pump Trip (EOC RPT)
Instrumentation................................................................... 3.3.4.1 1 Anticipated Transient VVithout Scram Recirculation Pump Trip (,A,Til\\/S RPT) Instrumentation............................ 3.3.4.2 1 Emergency Core Cooling System (ECCS)
Instrumentation................................................................... 3.3.5.1 1 Reactor Pressure Vessel (RP\\/) 'Nater Inventory Control Instrumentation................................................................... 3.3.5.2 1 Reactor Core Isolation Cooling (RCIC) System Instrumentation................................................................... 3.3.5.3 1 (continued)
Amendment Q1, 123, 138, 168
TABLE OF COMTEMTS
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3.3.6.1 3.3.6.2 3.3.7.1 3.3.7.2 3.3.S.1 3.3.S.2 3.3.S.3
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3..4..+
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3.4..4
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3.4.10
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3.6.1.1 3.6.1.2 3.6.1.3 3.6.1.4 3.6.1.5 3.6.1.6 3.6.1.7 3.6.2.1 3.6.2.2 3.6.2.3 3.6.2.4 INSTRUMEN+aTION (co t" 12i:*
h n inued}
imai:y Containment I I.
Secondai:y Contain so at1on lnsti:umentation Conlml Room En>"'~ont Isolation lnstrYmontati~~....................... J.J.6.1 1 lnslrYmontaiio~P* F1llrat1on (CREF) System***********************
J.J.6.:1 1 Mechanical 'lacu lnslrY,,;onla~: PYmp Isolation
.................................. J.J.7.1 1 Loss of 12owei: (LOl2~........................................
Reaotor Proto.ii S lnslFYm*nlalion...
........................... J.J.7.:1 1
--on - ystem (Rl2S Monitorin 9 l; iG)
Elocirio Power
................... J.J.8.1 1 Reactoi: 12rntection S ~ste.....................................
Monitorin" s y m (RPS) Elootrio P<>W9;************************
J.J.8.:1 1
- i ci:am Solenoids..............
.............................. J.J.8.J 1 Recii:culation Loops 0 YSTE_M (RCS}
Flow Contrnl Valves (/~~arg............................................
Jot Pw>ips s *************************
......... J.4.1 1 Satoty/Roli~i \\i;i~~~ (S iRii~).... * * -................ : : : : : : : : : : : : :... * * * * * * * * * * * * * * *
- J.4.:1 1 RCS Operational LE* 0.GE.................................................... J.4.J 1 RCS Prossyre I I '.' -
.....................
- J.4.4 1 RCS loaka ; ~o.ation \\/alve (PIV) l~~k~Q~............................... J.4.5 1 RCS Spooif~ AG:;~~t~ion 1 nstrYmontalion.. tt...
.............. J46 1 Res10Yal Heat Rom~,;~i -(fij:jfi)................................
................ J.U 1 System Hot s'h Shutdown Coolinn.................... 3.4.S 1 R
"d
--utdown es1 ual Heat Remo"al (R~*R..........................
s,..tem C Id$) ShYtdown Cooli~g *********************** J.4.Q 1 RCS 12i:essui:e an: ~ hutdovvn.................
Reaotor Steam D -9m perat""' (PIT) Lim ii~-..............................
- J.4.10 1 ome 12i:essui:e.........
- * * * * * * * * * * * * * * * * * * * * * * * * *..... 3.4.11 1 EMERGENCY CORE CO
.......................................... J.4.1:11
~66~TORY CONTROL :;~)~ A~YDs~:~s (ECCS), RPV WATER EC NG (RCIC) _SYSTEM
..CTOR CORE ISOLATION CS Opei:ating Reactoi: 12i:essui:e \\~~~~-1 -*(*R **\\*;**;~i******** *********************
RCIC System
--P *) - ater Inventory c ;* *
- j * * * * * * * * * * * *
- J.5.1 1 on rn.............. 3 5 2 1 CONTAINMENT SYSTEMS
.................................................. J:5:J 1 l2i:~mai:y Containment.
12nmai:y Cont.
Prima~ coni:::::nt Air looks......
....................................... U 1 1 1 Drywell anO S nt Isolation \\/al'J9s (PCiV~i"........................... J.6.1.:1 1 Drywell Air To yppross1on Chamber Prossyro............................ J.6.1.J 1 R.
mporatyro J 6 1 os1dYal Heat Romo"
- **************** *.4 1 Sypprossion Chamb. al (RHR) Drywell Spray
........................ J.6.1.5 1 SYpprossion Pool... *r to Drywell \\/aoYYm a,.."~k~;;;.................... J.6.1.6 1 Sypprossion Pool ;,*tra90 Tompora!Yr*...............
................... J.6.1.7 1 ResidYal Heat Ro;o~* *r lo'J91.............................. ***********************
J.6.:1.1 1 Coolin 9
. al (RHR) Sypprossion Pool ***********************
J.6.:1.:11 Residual Heat *R~~~ ;;~1 ******************************************
Spray (RHR) Sypprossion Pool *********************
J.6.:1.J 1
.................................................................................. 3.6.2.4 1 (continued}
A d
'.men ment Q1, 168
+-
TABLE OF CONTENTS
~
3.6.3.1 3.6.3.2 3.6.4.1 3.6.4.2 3.6.4.3
~
~
~
"4
~
~
~
~
~
~
~
~
~
~
~
~
~
3.10.1 3.10.2 3.10.3 CONTAINMENT SYSTEMS (continued)
Deleted........................................................................................ 3.6.3.1 1 Primary Containment Oxygen Concentration............................... 3.6.3.2 1 Secondary Containment.............................................................. 3.6.4.1 1 Secondary Containment Isolation Valves (SC IVs)....................... 3.6.4.2 1 Standby Gas Treatment (SGT) System........................................ 3.6.4.3 1 PL.A.NT SYSTEMS Service Water (SVV) System and Ultimate Heat Sink (UHS)......................................................................... 3.7.1 1 Control Room Envelope Filtration (CREF) System...................... 3.7.2 1 Control Room Envelope Air Conditioning (AC)
System............................................................................... 3.7.3 1 Main Condenser Offgas............................................................... 3.7.4 1 Main Turbine Bypass System...................................................... 3.7.5 1 Spent Fuel Storage Pool Water bevel.......................................... 3.7.6 1 ELECTRICAL POVVER SYSTEMS AC Sources Operating.............................................................. 3.8.1 1 AC Sources Shutdown.............................................................. 3.8.2 1 Diesel Fuel Oil, Lube Oil, and Starting Air.................................... 3.8.3 1 DC Sources Operating.............................................................. 3.8.4 1 DC Sources Shutdown............................................................. 3.8.5 1 Battery Cell Parameters............................................................... 3.8.6 1 Inverters Operating................................................................... 3.8.7 1 Distribution Systems Operating................................................ 3.8.8 1 Distribution Systems Shutdown................................................ 3.8.Q 1 REFUELING OPERATIONS Refueling Equipment Interlocks................................................... 3.9.1 1 Refuel Position One Rod Out Interlock........................................ 3.9.2 1 Control Rod Position.................................................................... 3.9.3 1 Control Rod Position Indication.................................................... 3.9.4 1 Control Rod OPERABILITY Refueling...................................... 3.9.5 1 Reactor Pressure Vessel (RPV) \\Nater Level Irradiated Fuel........................................................ 3.9.6 1 Reactor Pressure Vessel (RPV) Water bevel New Fuel or Control Rods...................................... 3.9.7 1 Residual Heat Removal (RHR)
High Water bevel..................... 3.9.8 1 Residual Heat Removal (RHR)
Lo1..v Water Level...................... 3.9.9 1 SPECIAL OPERATIONS System Leakage and Hydrostatic Testing Operation........................................................................... 3.10.1 1 Reactor Mode Switch Interlock Testing........................................ 3.10.2 1 Single Control Rod VVithdrawal Hot Shutdown.......................... 3.10.3 1 (continued)
Amendment Q1, 124
TABLE OF CONTENTS
~
3.10.4 3.10.5 3.10.6 3.10.7 3.10.B
~
~
5.-2 5.-3 M
~
5.6 f>;+_
SPECIAL OPERATIONS (continued)
Single Control Rod V\\lithdrawal Cold Shutdown........................ 3.10.4 1 Single Control Rod Drive (CRO)
Removal Refueling.......................................................... 3.10.5 1 Multiple Control Rod V\\lithdrawal Refueling............................... 3.10.6 1 Control Rod Testing Operating.................................................. 3.10.7 1 SHUTOOVVN MARGIN (SOM) Test Refueling........................... 3.10.6 1 DESIGN FEATURES Site Location............................................................................... 4.0 1 Reactor Core............................................................................... 4.0 1 Fuel Storage................................................................................ 4.0 2 ADMINISTRATIVE CONTROLS Responsibility.............................................................................. 5.1 1 Organization................................................................................ 5.2 1 Unit Staff Qualifications................................................................ 5.3 1 Procedures.................................................................................. 5.4 1 Programs and Manuals................................................................ 5.5 1 Reporting Requirements.............................................................. 5.6 1 High Radiation Area..................................................................... 5.7 1 Amendment 91
ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.9 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 Revised Technical Specification Pages Peach Bottom Unit 2 ii iii Peach Bottom Unit 3 ii iii
TABLE OF CONTENTS :-+/--
~
~
~
~
~
~
~
~
~
3.3. 1. 1 3.3. 1.2
- 3. 3. 2. 1 3.3. 2. 2
- 3. 3. 3. 1 3.3.3. 2 3.3.4. 1 3.3.4. 2
- 3. 3. 5. 1 3.3. 5. 2 3.3. 5.3 3.3. 5.4 3. 3. 6. 1 3.3.6. 2 3. 3. 7. 1 3.3.8. 1 3.3.8. 2 USE AND APPL ICAT ION
- 1. 1 1 Defi Ai t i oAs............................................... 1. 1 1 Logica l CoAAectors........................................ 1. 2 1 Compl et i GA Ti mes.......................................... 1. 3 1 FrequeAcy................................................. 1. 4 1 SAFETY LIMITS ( SLs)........................................... 2.0 1
-&-L *. *. *. *. *. *. *. *. *. *. *. *. *. *. *. *. *. *. *. *. *. *. *. *. *.
- 2.0 1 SL Viol atioAs............................................. 2.0 1 LIMI TING CONDITION FOR OPERAT ION (LCO) AP PLICABI LITY.......... 3.0 1 SURV EI LLANCE REQUI REME NT (SR) APPL ICABI LITY................... 3.0 4 REACT IVITY CONTROL SYSTEMS................................ 3. 1 1 SHUTDO'tJN MA RGIN (SOM)................................. 3. 1 1 React iv'ity AAomali es.................................. 3. 1 5 CoAtrol Rod OPERABI LIT¥............................... 3. 1 7 CoAtrol Rod Scram Times............................... 3. 1 12 CoAtrol Rod Scram Accumu l ators........................ 3. 1 15 Rod Pattern CoA t ro l................................... 3. 1 18 StaAdby Li quid CoAtrol (SLC) System................... 3. 1 20 Scram Disc har ge Vo l ume (S DV) VeAt aAd DraiA Va l ves.... 3. 1 26 PO'tJER DISTR IBUTimJ LHHTS................................. 3. 2 1 AV ERAG E PLANAR LINEAR HEAT GENERAT ION RAT E (APLHGR)........................................... 3. 2 1
~HN I MUM CRIT ICAL POIJER RATIO 04CP R)................... 3. 2 2 LINEAR HEAT GE NERAT ION RAT E (LHGR)................... 3. 2 4 HJSTRUME NTATIO N........................................... 3. 3 1 Reactor Protecti GA System (RPS) IAstrumeAtati GA....... 3. 3 1
'tJide RaAge
~J eu t roA MoA i tor
(
'tJR N~O IAs t rumeAta ti oA..... 3.3 10 CoAtrol Rod Bl eek IAstrumeAtati GA..................... 3. 3 16 Feedwa t er aAd Ma i A TurbiAe High Water Leve l Tr ip IAstrumeAtatioA.................................... 3.3 22 Post Acc i deAt MoAitoriA g (PAM) IAstrumeAtatioA........ 3.3 24 Remote Shutdo*vm System................................ 3.3 27 AAticipated TraAsieAt Without Scram Recirculat i oA Pump Trip (AHJS RPT) IAstrumeAtatioA............... 3.3 29 EAd of Cycl e Rec i rcu l at ioA Pump Trip (EOG RPT) IAstrumeAtatioA............. 3.3 31a t hru 3.3 31c EmergeAcy Core Cool iA g System (EGGS) IAstrumeAtatioA.. 3.3 32 Reactor Core Isol atioA Cool iA g (RC IC) System IAstrumeAtat i oA....................................
Not Used..............................................
Reactor Pressure Vesse l (R PV) Water IAveAtory CoAtrol IAstrumeAtatioA....................................
Pri mary CoAtaiAmeAt Isolat i oA IAstrumeAtat i oA.........
SecoAdary CoAtaiAmeAt IsolatioA IAstrumeAtatioA.......
Ma i A CoAtrol Room EmergeAcy VeAt i lat i oA (MCREV)
System IAstrumeAtatioA.............................
Loss of Pov.'er (LOP) IAstrumeAtat i GA...................
Reactor ProtectioA System (RPS) Electric Power
~1oAitoriAg............................................
3.3 44 3.3.47a j,.-
3.3.47b " I
- 3. 3 48 3.3 55
- 3. 3 59 3. 3 61 3.3 66 (COAt i Aued)
+
AmeAdmeAt No. 317
TABL E OF CONTE NTS (continued) :-4 ;-4--;-}
~ ;-4-; -3-:-4-:-4 ;-4--h :-4-: -3-;-4-; ~
- 3. 4. 10 : 3. 6. l. 1
- 3. 6. 1. 2
- 3. 6. 1.3
- 3. 6. 1. 4
- 3. 6. 1.5
- 3. 6. 1.6 3. 6. 2. 1
- 3. 6. 2. 2
- 3. 6. 2. 3
- 3. 6. 2. 4
- 3. 6. 2. 5 3. 6. 3. 1
- 3. 6. 3. 2
- 3. 6. 4. 1
- 3. 6. 4. 2
- 3. 6. 4. 3
~ :-7-: ~
PBAPS UN IT 2 REACTOR _COOLANT SYSTEM (RCS)
Rec1 rcu 1 at i L
J eeeeps Ope pa t i A§
- * * * * * * * * * * * *
- 3. 4 I et Pumps.
3 4 1 Safety Re1 i.e.f *v*a*,*.:e*s* *,*S*R*,; *)* * * * * * * * * * * * * * * * * * *. :....... 3
- 4 6
, v s
- andSf
~~S Ope pa ti eea l LEAKAGE,a ety Va h es I SVs)... 3. 4 8 S Leakage Bete t
- 3 4 RCS S e ' "" lestr*meetati ee
........... - IC pec1 f1 c Activity
- * * * * * * * * * * * *.... 3 4 12 Res *d 1
1 ua Heat Remova 1 ( RHRl Shu.td. *. ; * *C* * * *: * * * * * * * * * *.. 3. 4 14 System Hot Shutdo*.
o,,n 0011 ng esi ua1 Heat Remova 1 (RHRl* *S*h* * * * * * * * * * * * * * * * * * * * * * * *
- 3. 4 16 R
. d VI A * *
- System Co 1 d Shutd,,
utdmm Coo1 i ng RCS p OnA *
- R ressure and Temperatur*e* *,*P* ;Tl. *L: *:............... 3. 4 19
- 3. 4 21
- 3. 4 28 CO NTRO L (IJIC)
AN8 RE ACTOR CO (EGGS) ' RPV IJATER I NV E ~HORY SYSTE~1...... '
n RE I SOLATION COOLING (RCIC)
- 3. 5 1 EGGS..... : : : : : : : : : : : : : : * * * * * * * * * *..................... 3. 5 1 8e 1 eted RC I C Sys.le*~ *****
- ******* 3. 5 8
- 3. 5 12 h
ernventory Contro1
...................... 3. 5 13 CONTA I NMENT SYSTEMS Pr i mary Containment I 1
3 6 Drywel l Air Temperat: :: atiee Va l ves IPC ! Vs)... :::::::
- - 3 R
- 3. 6 8 eactor Bu i 1 ding to s * * * * * * * * * * * * * * * * * * * * *
- 3 Breakers
- ppressi ee C~am~er Vae**~ *
- * * * **** 6 17 s
uppress i on Chamber to. *8*r* :. ;... *,;...................... 3. 6 18
- 3. 6 21 Suppression Poo l A11erag}
Tvoe 11 oacuum Breakers.
n v ---e - empe t
- * * * * *
- 3. 6 23 Sup~ress i on Poo1 IJater Leve 1 ra ure.................. 3. 6 26 Res 1dua1 Heat Remova 1 (RHRl S....... *:.................
Coo1 i ng.......
uppress1 on Poo1 R
. d es~ ua1 Heat Remova 1 (RHRl. *S*u* * * * * * *: * * * * * * * * * * * * * *... 3. 6 27 Res1dua1 Heat Remova 1 (RHRl 8 ~~ress1on Poo1 Spray.... 3. 6 29 8e 1 eted r;,,e1 1 Spray Pri mary "c". *t. :....................
............. 3. 6 30a S
- "" ai emeet Oxnee Ceeeeet ;a*t
- ................ 3. 6 31 econ ary Containment........
i on **********
.... 3. 6 33 Secondary Containment I so1at i o*n* *,;a*1*.:...... *,;.......... 3. 6 34 Standby Gas Treatment (SGT) Syst~m ves (SC i osl........ 3. 6 36 p LANT SYSTD1S
.................... 3. 6 4C HE i g h Pres s.u. r.e. *S*e* r*v*i*c*e* *,~a.te. r.. (.H. P*S*, ;)*.S... t................ 3. 7 1 mergenc" s 6
YS em J _ er v1ce 'tJater (ESIJ)
- * * * * * * * *.... 3 7 1 Heat Si nk System and Norma 1 Emergency Heat *S*i*n*I;...................................
M *
- 3. 7 3 a i n S Cont re 1 Room Eme rg*e*n*c*,,,,; *v*e*n*t*1:, *a*t*:................. 3. 7 5 ystem J
i on (MCREVl
~1a i n Conde*n*s*e*r* "o".ff*g*a*s* * * * * * * * * * * * * * * * * * * * * * * * * *........ 3. 7 7
................................. 3. 7 10
++
Amendment No. 317
+
TABLE OF CONTENTS ;-S :-8-:-l-
~ :-8-:-3 ;-8-;-4 :-8-:- ~
~
~ : -3-:-9-:-l-
~ :-9-:-3
~
~
~ :-9-: ~
~
- 3. 10. 1
- 3. 10. 2
- 3. 10. 3
- 3. 10.4
- 3. 10. 5
- 3. 10. 6
- 3. 10. 7
- 3. 10.8 :-.Q. : -5-: ~ :-4 : -5-: ~
PLANT SYSTEMS (continued)
Main Turbine Bypass System............................ 3. 7 12 Spent Fuel Storage Pool \\J ate r Level................... 3. 7 14 ELECTRICAL POWER SYSTEMS.................................. 3.8 1 AC Sources Operating................................. 3. 8 1 AC Sources Shutdo*,m.................................. 3.8 20 Diesel Fuel Oil, Lube Oil, and Starting Air........... 3.8 25 DC Sources Operating................................. 3. 8 28 DC Sources Shutdo*,m.................................. 3.8 34 Battery Cell Parameters............................... 3.8 37 Distribution Systems Operating....................... 3.8 41 Distribution Systems Shutdown........................ 3.8 44 REFUELHJG OPERATIONS...................................... 3. 9 1 Refueling Equipment Interlocks........................ 3. 9 1 Refuel Position One Rod Out Interlock................. 3. 9 3 Control Rod Position.................................. 3. 9 5 Control Rod Position Indication....................... 3. 9 6 Control Rod OPERABI LIT¥ Refueling.................... 3. 9 8 Reactor Pressure Vessel ( RPV l 'tJater Lev'el............. 3. 9 9 Residual Heat Removal (RHRl High IJater Level......... 3. 9 10 Residual Heat Removal (RHRl Loh' 'tJater Level.......... 3. 9 13 SPECIAL OPERATIONS........................................ 3. 10 1 Inservice Leak and Hydrostatic Testing Operation...... 3. 10 1 Reactor Mode Switch Interlock Testing................. 3. 10 4 Single Control Rod IJi thdra'"'al Hot Shutdmm........... 3. 10 6 Single Control Rod IJi thdravo'al Cold Shutdo*11*n.......... 3. 10 9 Single Control Rod Drive (CRDl Removal Refueling................................. 3. 10 13
~1ul ti pl e Control Rod IJi thdra'n'al Refueling............ 3. 10 16 Control Rod Testing Operating........................ 3. 10 18 SHUTDOWN MARGIN (SOM) Test Refueling................. 3. 10 20 DESIGN FEATURES............................................... 4. 0 1
~ +.-o-Re actor Core.............................................. 4. 0 1 Fuel Storage.............................................. 4. 0 2 AmHN ISTRATIVE cmnROLS....................................... 5. 0 1 Responsibility............................................ 5. 0 1 Organization.............................................. 5. 0 2 Unit Staff Qual i fi ca ti ens................................. 5. 0 5 Procedures................................................ 5. 0 6 Programs and Manuals...................................... 5. 0 7 Reporting Requirements.................................... 5. 0 18 High Radiation Areas...................................... 5. 0 22 PBAPS UN IT 2 Amendment No. 210
TABLE OF CONTENTS :-+/--
~
~
~
~
~
~
~
~
~
3.3. 1. 1 3.3. 1.2
- 3. 3. 2. 1 3.3. 2. 2
- 3. 3. 3. 1 3.3.3. 2 3.3.4. 1 3.3.4. 2 3. 3. 5. 1 3.3. 5. 2 3.3. 5.3 3.3. 5.4 3. 3. 6. 1 3.3.6. 2 3. 3. 7. 1 3.3.8. 1 3.3.8. 2 USE AND APPL ICAT ION
- 1. 1 1 Defi Ai t i oAs............................................... 1. 1 1 Logica l CoAAectors........................................ 1. 2 1 Compl et i GA Ti mes.......................................... 1. 3 1 FrequeAcy................................................. 1. 4 1 SAFETY LIMITS ( SLs)........................................... 2.0 1
-&-L *. *. *. *. *. *. *. *. *. *. *. *. *. *. *. *. *. *. *. *. *. *. *. *. *.
- 2.0 1 SL Viol atioAs............................................. 2.0 1 LIMI TING CONDITION FOR OPERAT ION (LCO) AP PLICABI LITY.......... 3.0 1 SURV EI LLANCE REQUI REME NT (SR) APPL ICABI LITY................... 3.0 4 REACT IVITY CONTROL SYSTEMS................................ 3. 1 1 SHUTDO'tJN MA RGIN (SOM)................................. 3. 1 1 React iv'ity AAomali es.................................. 3. 1 5 CoAtrol Rod OPERABI LIT¥............................... 3. 1 7 CoAtrol Rod Scram Times............................... 3. 1 12 CoAtrol Rod Scram Accumu l ators........................ 3. 1 15 Rod Pattern CoA t ro l................................... 3. 1 18 StaAdby Li quid CoAtrol (SLC) System................... 3. 1 20 Scram Disc har ge Vo l ume (S DV) VeAt aAd DraiA Va l ves.... 3. 1 26 PO'tJER DISTR IBUTimJ LHHTS................................. 3. 2 1 AV ERAG E PLANAR LINEAR HEAT GENERAT ION RAT E (APLHGR)........................................... 3. 2 1
~HN I MUM CRIT ICAL POIJER RATIO 04CP R)................... 3. 2 2 LINEAR HEAT GE NERAT ION RAT E (LHGR)................... 3. 2 4 HJSTRUME NTATIO N........................................... 3. 3 1 Reactor Protecti GA System (RPS) IAstrumeAtati GA....... 3. 3 1
'tJide RaAge
~J eu t roA MoA i tor
(
'tJR N~O IAs t rumeAta ti oA..... 3.3 10 CoAtrol Rod Bl eek IAstrumeAtati GA..................... 3. 3 16 Feedwa t er aAd Ma i A TurbiAe High Water Leve l Tr ip IAstrumeAtatioA.................................... 3.3 22 Post Acc i deAt MoAitoriA g (PAM) IAstrumeAtatioA........ 3.3 24 Remote Shutdo*vm System................................ 3.3 27 AAticipated TraAsieAt Without Scram Recirculat i oA Pump Trip (AHJS RPT) IAstrumeAtatioA............... 3.3 29 EAd of Cycl e Rec i rcu l at ioA Pump Trip (EOG RPT) IAstrumeAtatioA.....
3.3 31a thru 3.3 31c EmergeAcy Core Cool iA g System (EGGS) IAstrumeAtatioA.. 3.3 32 Reactor Core Isol atioA Cool iA g (RC IC) System IAstrumeAtat i oA....................................
Not Used..............................................
Reactor Pressure Vesse l (R PV) Water IAveAtory CoAtrol IAstrumeAtatioA....................................
Pri mary CoAtaiAmeAt Isolat i oA IAstrumeAtat i oA.........
SecoAdary CoAtaiAmeAt IsolatioA IAstrumeAtatioA.......
Ma i A CoAtrol Room EmergeAcy VeAt i lat i oA (MCREV)
System IAstrumeAtatioA.............................
Loss of Pov.'er (LOP) IAstrumeAtat i GA...................
Reactor ProtectioA System (RPS) Electric Power
~1oAitoriAg............................................
3.3 44 3.3.47at 3.3.47b 3.3 48 3. 3 55 3.3 59 3. 3 61 PBAPS UN IT 3
+
AmeAdmeAt No. 320
TABLE OF CON TEN TS (continue d) ;-4 :-4-:--l-
~ :-4-:-3 ;-4-;-4 :-4-: -3-;-4-; -3-:-4-: -3-:-4-: 3. 4. 10 : 3. 6. l. 1
- 3. 6. 1.2
- 3. 6. 1. 3
- 3. 6. 1.4
- 3. 6. 1. 5
- 3. 6. 1. 6 3. 6. 2. 1
- 3. 6. 2. 2
- 3. 6. 2. 3
- 3. 6. 2. 4
- 3. 6. 2. 5 3. 6. 3. 1
- 3. 6. 3. 2
- 3. 6. 4. 1
- 3. 6. 4. 2
- 3. 6. 4. 3
~ :-7-:-l-
~
PBAPS UN IT 3 REACTOR _COO LANT SYST EM (RCS)
Recircu1ation Loops Opera.ti*n****** * * ****** * * ****** * * *** 3. 4 1 Jet Pumps g * * * * * * * * * * * * *...
3 4 1 Safety Re1*i*e*f *v*a*1*v*e*s* *(*S*R"*s*)* *a*n*d* * * * * * * * * * * * * * * ::::::::: 3:4 6 RCS Operat i ona 1 LEAKAG E v Safety Va h es (SVs)... 3. 4 8 RCS Leakage Bet t
- 3 RCS S
. ~ee iee Iestr*meetatiee
.............. 4 lC
. pec 1f 1c Act i vi ty
- * * * * * * * * * * * *.... 3 4 12 Res d i
ua, Heat Remova 1 ( RHR ) *s* * * * * * * * * * * * * * * * * * * * * * * *.. 3 4 14 System Hot Shut d,,
hutdo*,m Coo1 i ng Res
- d 1
°"n * * *
- 1 ua Heat Remova 1 ( RHR ) * * * * * * * * * * * * * * * * * * * * * * * * *.. 3. 4 16 System Co1 d Shut do* *n Shutdo*,m Coo1 i ng RCS Pressure d
R an Temperature (P IT) L".
- 3. 4 19
- 3. 4 21
- 3. 4 28 CONTROL (IJIC) ' AN 8 RE ACTO R C
( EGGS) ' RPV IJATER I NVE~HORY SYST EM ORE I SOLAT I ON COOL ING ( RCI C)
- 3. 5 1 EGGS 8elete*d* * * * * * * * * * * * * * * * * * * * *........... : : : * * * * * * * * * * * *
- 3. 5 1 RC I C Sys.le*~ ******************************
- *** 3. 5 8
- 3. 5 12 h
ernven t ory Con t ro 1
...................... 3. 5 13 t CONTA INM ENT SYSTEMS Prlfflary Containment I 1
3 6 Dry11ell ' i T
50 atiae la l ves (PC l"sl
- * * *.. - 3 Reactor Bui 1 ding to s * * * * * * * * * * * * * * * * * * * * *
- 3 6 Breakers
'~~re ss iee CAamBer Vae"~ * * * * * * *.. - 17 s
uppression Chamber to
- ~ ;
~
Sup press i on Poo1 A,,
,y.. ei i vacuum Breakers
- 3. 6 18
- 3. 6 21 n verage Tempe t
- * * * *.. 3. 6 23 Sup ~ ressi on Poo1 IJater Leve1 ra ure.................. 3. 6 26 Res1 dua1 Heat Remova 1 (RHR) S....... *:.................
Coo1ing.......
up press 1on Poo1 R
. d es~ ua1 Heat Remova 1 (RHR)* *S*u**** * * *:**** * * ****** * * *** 3. 6 2t Res 1dua1 Heat Remova 1 ( RHR ) 8 ~ ~ ress 1 on Poo1 Spray.... 3. 6 29 8e1 ete d r),,e1 1 Spray Primary *c;,*t,*:***************************
- 3.6 30a Seeee~ary Cee::::::,:~gee ! eeeeetratiee.............. ~:: ~~
Secondary Genta i nment I so1 ati o.n. *,;a*".:...... *,;.......... 3. 6 34 Stan dby Gas Treatment (SGT) Sys t ; m1 ves (SC I vs)........ 3. 6 36 PLANT SYST EMS
.................... 3.6 4C HE i g h Press. u. r.e. *S*e* r. v. i. c.e. *,~ a.te. r.. (. H*P*S*,; ).. S. :.t................ 3. 7 1 mergenc" s h)S em J _ erv 1ce 'tJater (ESIJ)
- * * * * * * * *.... 3 7 1 Heat S1 nk System and
~J orma 1 Emergency Heat *S*i*n*I;..........................
~1 ai n Contro1 Room E * * * * * * * * * * * * * * * * *......... :. * * * * * *
- 33 * ~ 3 m
mergeAC""
11e t "1 r 5 System J
on 11 at1 on (MC RE V)
~1 a i n Con de*n*s*e* r. 'o'-f f*g*a*s* * * * * * * * * * * * * * * * * * * * * * * * * *........ 3. 7 7
................................. 3. t 10
++
Amen dment No. 320
TABLE OF CON TEN TS :-B ;-8-;-}
~ ;-8-; -3-:-8-:-4 ;-8-; -3-:-8-: ~
~ : ~
~
~ :-9-:-4
~
~
~
~
~
- 3. 10. 1
- 3. 10. 2
- 3. 10.3
- 3. 10. 4
- 3. 10. 5
- 3. 10. 6
- 3. 10. 7
- 3. 10.8 : -5-: -5-: ~ :-4
~ : -5-: PLANT SYST EMS (cont i nued)
Mai n Turbine By pass System............................ 3. 7 12 Spent Fue l Storage Poo l l.'ater Leve l................... 3. 7 14 ELECT RI CAL POW ER SYSTEMS.................................. 3.8 1 AC Sources Operatin g................................. 3. 8 1 AC Sources Shutdo*vm.................................. 3.8 20 Diesel Fue l Oi l, Lube Oi l, and Start i ng Air........... 3.8 25 DC Sources Operating................................. 3. 8 28 DC Sources Shutdo*vm.................................. 3.8 34 Battery Ce l l Parameters............................... 3.8 37 Di stri bu ti on Systems Operatin g....................... 3. 8 41 Distribution Systems Shutdown........................ 3.8 44 REFUELHJG OPERATIONS...................................... 3. 9 1 Refuel i ng Equipment I nt erlocks........................ 3. 9 1 Refuel Position One Rod Out I nterlock................. 3. 9 3 Contro l Rod Position.................................. 3. 9 5 Contro l Rod Position I ndication....................... 3. 9 6 Contro l Rod OPERABI LIT¥ Refuel i ng.................... 3. 9 8 Reactor Pressure Vesse l ( RPV) 'tlater Leve l............. 3. 9 9 Residual Heat Remova l (RHR)
High IJater Level......... 3. 9 10 Residual Heat Remova l (RHR )
Lo'ii' 'tlater Le1i*el.......... 3. 9 13 SP ECI AL OPERATIONS........................................ 3. 10 1 I nserv i ce Leak and Hydrostat i c Testin g Operation...... 3. 10 1 Reactor Mode Switc h I nterlock Testing................. 3. 10 4 Sin gl e Control Rod IJi t hdravo'a l Hot Shutdmm........... 3. 10 6 Sing l e Control Rod IJ i t hdra*,.*al Co l d Shutdo*,m.......... 3. 10 9 Sin gl e Control Rod Drive (CRD)
Remo1i*al Refueling................................. 3. 10 13
~1 u l t i pl e Control Rod IJi t hdra'ii'a l Refuel i ng............ 3. 10 16 Contro l Rod Testing Operating........................ 3. 10 18 SHUTDO'tlN MARG I N (S OM) Test Refue l in g................. 3. 10 20 DES I GN FEATURES............................................... 4. 0 1
.s+t-e
................................................... 4. 0 1 Reactor Core.............................................. 4. 0 1 Fuel Storage.............................................. 4. 0 2 AmHN I STRATIV E cmn ROLS....................................... 5. 0 1 Res ponsibi l ity............................................ 5. 0 1 Organization.............................................. 5. 0 2 Un i t Staff Qua l i fi ca ti ens................................. 5. 0 5 Procedures................................................ 5. 0 6 Pro grams and Manua l s...................................... 5. 0 7 Reporting Requirements.................................... 5. 0 19 Hig h Rad i ation Areas...................................... 5. 0 23 PBAPS UN IT 3 Amendment 214
ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.10 Quad Cities Nuclear Power Station, Units 1and2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 Revised Technical Specification Pages i
ii iii iv
TABLE OF CONTEN TS ;-} :-l--: ~
~ :-+.-4 :-l--: -3-:-l--: -3-+: -3-:-+.-8 :-3
- 3. 3. 1. 1
- 3. 3. 1. 2
- 3. 3. 1. 3
- 3. 3. 2. l
- 3. 3. 2. 2
- 3. 3. 3. l
- 3. 3.4. l
- 3. 3. 5. 1
- 3. 3. 5. 2
- 3. 3. 5. 3
- 3. 3. 6. l
- 3. 3. 6. 2 3.3.6.3 USE AND APP LICAT ION Definitions Log i ca l Con~~~ t ~~; * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *. 1. 1 1 Complet i on Ti mes. * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *. 1. 2 1 Frequency
- * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- 1. 3 1
................................................ 1. 4 1 SAFETY LIMI TS (SLsl S Ls. :.......................................
2 0 1 SL Vio l at i ons
~
............................................ 2. 0 1 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY 1
SURVE I LLA NCE REQUI REMENT (SR) APPL ICAB ILITY
....... *3*8
................. 3. 0 4 REACT IVITY CO NTROL SYSTEMS SHUTDOWN MARGIN (SDM)
React i vi ty Anomalies * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *. 3. 1. 1 1 Contro l Rod OPERABIL i TY..................... * * * * * * * * * * * *. 3. 1. 2 1 Contro l Rod Scram Ti mes **********************************
3. 1. 3 1 Contro l Rod Scram Accum~ i ~t~~;
- * * * * * * * * * * * * * * * * * * * * * * * * *. 3. 1.4 1 Rod Pattern Contro l
- * * * * * * * * * * * * * * * * * * * * * * * * *
- 3. 1. 5 1 Standby Li qu i d Cont~~ i * ( SLC )
- 5;, ;t~~ * * * * * * * * * * * * * * * * * * * * *
- b ~~ ~ ~ *~* i ~* * * * * * * * *3*1*7 1 oa ves....... 3. 1. 8 1 POWER DI STR IBUTION LIMITS AVERAGE PLA NAR LI NEAR HEAT GE NERATIO N RATE (APLHGR) 3 1
MINI MUM CR ITICAL POWER RAT IO (MCPR).
.... * * *2*1 LINEAR HEAT GENERATION RATE (LHGR)
..................... 3. 2. 2 1
...................... 3. 2. 3 1 I ~J STRU~4 E
~HATI O ~J Reactor Protect i on System (RPS) Instrumentation Sou~ce Range Monitor (SRM) Instrumentation
......... * ~
- 3. 1
. l 1 Osc ill at i on p R
- * * * * * * * * * * * * * *.3 1 2 1 Cowerange Mon i tor (OPRM) Instrumentation 3 3. 1. 3 1 ontro l Rod Bl ock Instrumentat i on Feed~ater System and Ma i n Turb i ne * ~~~ ~ * ~ ~t~~
- L~~~i * * * * * * *3*3*2*1 1 Trip Instrumentation
~ os ~ ~cc id ent Mon ~ tor i ~ ~ * (~ ~ ~)
- i ~;t~ ~ ~~~t~t ~ ~~ :::::::::: : ~ * ~ * ~
- 2 1 nnt i ci pat?d Trans i ent Wi thout Scram Recirculation
... l l Pump Trip (ATWS RPT) Instrumentat i on Pr imary Conta i nment I so i ~ t~ ~~
- i ~;t ~ ~ ~~~t~t ~ ~~ * * * * * * * * * * * * ~ * ~ * ~
- 3 1 Sec?ndary Conta i nment Iso l at i on Instrumentat i ~~ * * * * * * * * * *3*3*6*21 1 Re li ef Va l ve Instrumentat i on
- * * * * * * * * * * * * -l
............................. 3. 3. 6. 3 1 (cont i nued)
Quad Ci t i es 1 an d 2
+
Amen dment No. 273/268
TA BLE OF CONTEN TS
~. 7
. 1 IN STRUMEN TATIO N (ee t:
- Cent:re l Rn inued) eem Emergene:Y 11 t:.
Inst:rument:at: i en oen i lat: i en (GREV) System 3.3. 7.2 3.3.8. 1 3.3.8.2 :-4 :-4-: ~ :-4-= -3-:-4-:-4 :-4-: -3-:+. -3-:-4-: ~
3.4. 10 : 3. 6. l. 1 3.6. 1. 2 3.6. 1. 3 3.6. 1. 4 3.6. 1. 5 3.6. 1. 6 3.6. 1. 7 3.6. 1. 8 3.6.2. 1 3.6.2.2 3.6.2.3 3.6.2.4 3.6.2. 5 3.6.3. 1 3.6.4. 1 3.6.4.2 3.6.4.3 Meehani ea l iiaeuum. P.................
-- - um13 T.
Loss of PoweP ILOPI
- - rip l estremeetatioR.............. 3.3. 7.1 1 ReactoP PPotect
- l estremeetatioR.
.............. 3. 3. 7. 2 1 1 en S:yst:
(
MoettoPiRg
- --** *RPS) Electric Po".***********
.3.3.8.1 1 ooe r Safety., ~ - R~ ii ~f ","," i............... :: *******************
3.4.1 1 RGS va- *es 3
Opepati oAa l LEAKAGE
........................ :........ 4. 2 1 RGS Leakage Detec.
- * * * * *.3.4.3 1 RGS Spec i f i c ' ct "tl OR IRS t PemeetatioR
............. 3.4.4 1 R
1 I/ 1 :f::Y Res i <lea l Heat Remo **a;....................
............. 3.4.5 1 System Het: Shut:d *** (RHR) Shut:dewn Ceel ~ ~ 9* * * * * * * * * * * * *.3.4.6 1 Res id l
enn.
ua Hea t: Remeva l * * * * * * * * * * * * * * * * * * *...
System Gol <l S ~ et<l.. IRHRI S ~ e t <lowR Gool i Rg...... ** ** **.3.4. 7 1 RCS Pressure and T enn......................
ReactoP Steam Dom *:pePatePe IP / Tl Limits
............. 3.4.8 1 e
ressure...........
................ 3.4.9 1
~MERGE N GY GORE GOO LI NG S
................... 3.4.10 1
,J A TE R HJ \\I E
~H 0 y s TE Ms ( E c c s )
R E A
SYSTEM
- --- RY GO NTRO L' AND REAGTOR GoRE "i~~~ ' PRES SU RE VESSEL I RPV I ~
EGGS OpePati R nTION GOOL ING IRG IG)
RP" II t:
g...........
v "aer In**e t:
RG IG System v-R- ory GoRtPol....... :: ::................... 3.5. l 1
................... 3. 5 2 1
~
GO NTA INME NT SYSTEMS
................. ** ** **.3. 5:3 1 Pr ~ mary Cent:a i nment:
Pr i mary Cent:a i nment: *;:....................
PPimaPy Goetaiemee; "Lock.............. : *............. 3.6.1. l 1 Dpy11ell Ppessepe.. l sol at10R Val ves IPG !Vsi::........... 3.6.1.2 1 Dpy11ell Ai ' Tempe pat......................
........... 3. 6.1. 3 1 Lo" s t ere
- 3 6 1 4
" -e-Relief Valves
...... -.-. -.- 1 ReactoP Bei l <liRg t S.. * * * * * * *......
..... * * * *.3.6.1. 5 1 Breakers e
u1313ressien Cham~~~ *~ a* e*.............. 3.6. 1.6 1 S
v UUm u1313ress i en Chamb~~
- t *
- B * * * * * * * *...........
S O - Py* 'Cl l "
3 6 eppress i oR Pool *..
vaceem BPeakePS
- * * * * * *.-.-.1. 7 1 SeppPessioR Pool ~ * :rage TempePatere.....
- ** ** ** **.3.6.1.8 1 R *a
"' er Le**el 3 6 es 1 ea l Hea t Remova l IR~ * - *................... :........... 2.1 1 Resi <lea l Heat Remova l IRHRI SeppressioR Pool Gooi :*******3.6.2.2 1 Dpy11ell to SeppPess i RI SeppressioR Pool S r '.' §*.... 3.6.2.3 1 Pp1mapy Goetaiemeet :'~ ~ amber Differeet i al Pr! ay....... 3.6.2.4 1 Secoe <lapy Goe t a "
- )§CR GORECRtPatioR SSOPe..... 3.6.2. 5 1 S
lRmeet 3
ecoe<lapy Goeta i RmeRt.. *****:****************
............ 6.3.1 1 Stae<lby Gas Tpeatmeet ::ol at 10R Valves ISG !Vsi : *......... 3.6.4. l 1 GT) System.....
- * * * * * * * *.3.6.4.2 1
.................. 3.6.4.3 1 Qua d Citi es 1 an d 2 (eent: i nued)
Amen dmen t: Ne. 273/268
TABLE OF CONTEN TS (con t inued)
~
'3-:-t-:-+/-- :-7--: -3-:-7--:-3 :-t-:-4 :-f-:-5. :-B :-8-: ~
~ :-B-:-4
~
~
~ :-B-:-8 :4
~ :-9--:-6 :-9-: -3-;-9-;-4
~ :-9-: ~
- 3. 10. l
- 3. 10. 2
- 3. 10. 3
- 3. 10.4
- 3. 10. 5
- 3. 10. 6
- 3. 10. 7
- 3. 10.8 PLA NT SYSTEMS Res id ua l Heat Removal Serv i ce 'tJater (R HRSIJ) System....... 3. 7. 1 1 Di es el Generator Coo l in g 'tJater ( DGC IJ ) System............. 3. 7. 2 1 Ul timate Heat Sink (UHS)................................. 3. 7. 3 1 Cont rol Room Eme rgency Vent il at i on (GREV) System......... 3. 7.4 1 Contro l Room Emergency Vent i lat i on Ai r Con dit i on i ng (AC) System............................... 3. 7. 5 1 Main Condenser Off gas.................................... 3. 7. 6 1 Main Turbine Bypass System............................... 3. 7. 7 1 S p e n t F u e l S t o r a g e P o o l \\J a t e r Le v e l...................... 3. 7. 8 1 Safe Shutdown Makeup Pump (SSMP) System.................. 3. 7. 9 1 ELECTR ICAL POWER SYSTEMS AC Sources Opera ti ng..................................... 3.8. l 1 AC So urces Shutdo*,m...................................... 3. 8. 2 1 Di es el Fue l Oil Propert i es and Starting Air.............. 3. 8. 3 1 DC Sources Operating..................................... 3.8.4 1 DC Sources Shutdo*,;n...................................... 3. 8. 5 1 Battery Cell Parameters.................................. 3.8. 6 1 Di str i but i on Systems Operat i ng........................... 3.8. 7 1 Distribution Systems Shutdown............................ 3.8.8 1 REFU ELI NG OP ERATIO NS Refue li ng Equ i pment Inter l ocks........................... 3. 9. l 1 Refue l Position One Rod Out Inter l ock.................... 3. 9. 2 1 Con t ro l Rod Pos iti on..................................... 3. 9. 3 1 Contro l Rod Pos i t i on Ind i cat i on.......................... 3. 9.4 1 Contro l Rod OP ERA BI LITY Refue li ng........................ 3. 9. 5 1 Reactor Pressure Vesse l (RPV) Water Leve l Irra di at ed Fue l.................................. 3. 9. 6 1 Reactor Pressure Vesse l (RPV) Water Level New Fue l or Contro l Rods................................... 3. 9. 7 1 Residua l Heat Remova l (RHR) High l.'ater Leve l............. 3. 9.8 1 Res i du a l He a t Remo v a l ( RH R ) Lo.,, \\J a t e r Leve l.............. 3. 9. 9 1 SP ECIAL OP ERAT IONS Reactor Mode Switc h Inter l ock Testing.................... 3. 10. l 1 Si n g l e Contro l Rod l.'i th d r a *o1a l Ho t Shut d o~m............... 3. 10. 2 1 Si ng l e Contro l Rod Wi t hdrawa l Co l d Shutdown.............. 3. 10. 3 1 Si ng l e Contro l Rod Dr i ve (CRD)
Remova l Refueling...................................... 3. 10. 4 1 Mult i pl e Con t ro l Rod \\J it h d r m1a l Refue l i n g................ 3. 10. 5 1 Contro l Rod Test i ng Operat i ng............................ 3. 10. 6 1 SHUTDOW N MARG IN (SDM) Test Refue li ng..................... 3. 10. 7 1 Inservice Leak and Hydrostatic Testing Operation......... 3. 10.8 1 --h (cont i nued)
Qua d Citi es 1 an d 2 Amen dmen t No. 261 / 256
TABLE OF CO NTE NTS (continued)
~
DES I GN FEATURES 4-:-+/-
Si te Locat i on............................................ 4. 0 1
~
Reactor Core............................................. 4. 0 1 4-:-3 Fu el Sto r age............................................. 4. 0 2
~
ADMI NISTRATIVE CO NTROLS : Respons i bi li t y........................................... 5. 1 1 : Or ganization............................................. 5. 2 1 : Unit Staff Qua l ifi cations................................ 5. 3 1 :-4 Procedures............................................... 5. 4 1 : Programs and Manua l s..................................... 5. 5 1 : Repo r t i ng Requ i rements................................... 5. 6 1 : High Radiati on Ar ea...................................... 5. 7 1 Quad Ci t i es 1 and 2 Amendment
~J o
. 199 /1 95