ML20205D827

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Application for Amend to License DPR-59,converting CTS to Be Consistent with Improved Std TS in NUREG-1433,Rev 1
ML20205D827
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 03/26/1999
From: James Knubel
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20205D824 List:
References
RTR-NUREG-1433 NUDOCS 9904050010
Download: ML20205D827 (22)
v • d • e


Text

I BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION i in the Matter of )

POWER AUTHORITY OF THE STATE OF NEW YORK ) Docket No. 50-333 l James A. FitzPatrick Nuclear Power Plant )

APPLICATION FOR AMENDMENT TO THE OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the Nuclear Regulatory Commission, the Power Authority of the State of New York, as holder of Facility Operating License No. DPR-59, hereby applies for an amendment to the Technical Specifications contained in Appendices A and B of this license.

This application for amendment to the FitzPatrick Technical Specifications proposes to convert the FitzPatrick current Technical Specifications (CTS) to be consistent with the improved Standard Technical Specifications (ISTS) in NUREG-1433, Revision 1, dated April 1995. The proposed license cmendment request was prepared considering the guidance of Nuclear Energy Institute (NEI) NEl 96-06, " Improved Technical Specifications Conversion Guidance," dated August 1996.

The Proposed license amendment request to convert the FitzPatrick CTS to the FitzPatrick Improved Technical Specification (ITS) is enclosed with this application.

POWEh AUTHORITY OF THE STATEO. W YO D '

/ (

J.Knubel

, Senior Vice President and

/ Chief Nuclear Officer STATE OF NEW YORK COUNTY OF Subscribed and S yorn to before me t 6 day of muh .1999.

Au h (A Notary Public/

SERMDME STRAf40 hunury Pubhc. stese er see,w No 4991272 in Westchester

. Empres Jon 37, oD 9904050010 990331 "

PDR P

ADOCK 05000333fl  !

PDR j

Attachment 1 JPN 99 008 Page 1 of 7 ATTACHMENT 1 TO JPN-99-008 Synopsis of the License Amendment Request for Conversion to Improved Technical Specifications (ITS) i

Attachment 1 JPN 99 008 Page 2 of 7 The submittal for the conversion of the JAFNPP current Technical.

Specifications (CTS) to the JAFNPP Improved Technical Specifications (ITS) consists of five (5) sections collected into 19 volumes. The 5 sections of the conversion submittal are as follows:

I. Application of NRC Selection Criteria including the CTS to ITS .

Disposition and Relocation Matrix (Split Report);

II. FitzPatrick ITS Specifications and ITS Bases:

III. FitzPatrick CTS Master Markup:

IV. FitzPatrick Conversion Packages and Relocated Requirements -

Descriptions and Justifications for the conversion of FitzPatrick CTS to FitzPatrick ITS, and Descriptions and Justifications for the relocation of selected FitzPatrick CTS requirements and details; and V. Evaluations supporting a finding of No Significant Hazards Contiderr. twas (NSHC) as required by 10 CFR 50.91(a) for proposed changes classified as Administrative (A), More Restrictive (M),

Removed Detail (LA and LB) or. Relocated (R) (Note that NSHCs for changes classified as Less Restrictive (L) are included in Section IV.

A detailed description of each of these 5 sections is as follow:

Section I: Application of NRC Selection Criteria including the CTS to ITS Disposition and Relocation Matrix (Split Report)

Section I (Volu:ae 1 of the submittal) is an explanation of the process and a summary of the results of the application of the 10 CFR 50.36(c)(2)(ii) criteria for which requirements must be classified as Technical Specifications. The "NRC Selection Criteria" document provides a discussion of how the criteria of 10 CFR 50.36(c)(2)(ii) were applied to the James A.

FitzPatrick Nuclear Power Plant CTS requirements. The "ITS Disposition and Relocation Matrix" (Split Report) presents a summary of the results of this process by listing each CTS specification and whether or not the CTS specification is retained in the JAFNPP ITS. If retained in the JAFNPP ITS, the matrix identifies the new ITS specification number, the criterion of 10 CFR 50.36(c)(2)(ii) that applies and the basis for inclusion of the requirement in the Improved Technical Specifications. If not retained in the JAFNPP ITS, the matrix identifies the Section IV subsection that provides the detailed justification for relocation and the proposed new location for

Attachment ~1 JPN 99 008 Page 3 of 7 relocated requirements.

SECTION II. JAFNPP ITS Specifications and ITS BasesSection II (Volumes 2, 3 and 4 of the submittal).is a copy of the FitzPatrick ITS. Specifications and ITS Bases presented in their complete form to facilitate the review of the document in an integrated manner.

SECTION III. JAFNPP CTS Master Markup Section III (Volume 5 of the submittal) is a copy of all of the CTS pages that were annotated to show differences between CTS and ITS for the 141 packages in Section IV, presented in the order of the ITS.Section III is a compilation volume which provides a markup of the entire CTS (in CTS order) to facilitate NRC review efforts and to demonstrate that all CTS requirements have been arpropriately dispositioned. In many instances, the same CTS page is used in different ITS sections. As a result, in the compilation volume, the CTS pages that are included in more than one ITS Specification package will appear with the annotations associated with each ITS Specification package in which the CTS page appears.

SECTION IV. Descriptions and Justifications for the conversion of FitzPatrick current Technical Specifications to FitzPatrick Improved Technical Specifications and Descriptions and Justifications for the relocation of selected FitzPatrick Current Technical Specifications (CTS) (Volumes 6 through 18 and part of Volume 19 of the submittal).

This Section consists of 141 subsections (which are listed in Attachment 2),

one for each of the proposed JAFNPP Improved Technical Specifications. To facilitate both the NYPA and NRC review, each subsection contains the information necessary for review of one proposed FitzPatrick Specification.

Each of the 141 subsections is divided into 8 parts as follows:

Part I consists of the current Technical Specification pages annotated to show the differences between the CTS and the JAFNPP Improved Technical Specification (CTS Markup). These " CTS Markups" also provide a cross reference to the equivalent ITS requirement in both Part 1 and Part 5 of the subsection. Where a proposed ITS requirement differs from a CTS requirement, individual details of the CTS revision are annotated with alphanumeric designators which relate to the appropriate Discussion of Change (DOC) which is included in Part 2 of the subsection. The alphanumeric designators also relate to the evaluations supporting a

finding of No Significant Hazards Considerations'(NSHC) which is
included in Part 3 of the subsection. All unapproved License Amendment L

[

Attachment'l

.JPN 99 008 Page 4 of 7 Requests docketed as of November 1,.1998'are incorporated into the ITS conversion package and are listed in Attachment 3..

Part 2 consists of a Discussion of Change (DOC) for each of the differences between the CTS and the' proposed ITS. The changes.are listed by the alphanumeric designators which provide a cross reference to the CTS Markup contained in Part 1, the NSHC contained in Part 3, and-the ITS Markup contained in Part 4. Each DOC includes'a reference to and description of both the CTS and ITS requirements being discussed, the reason the change is needed, and a detailed justification that the

. proposed change does not result in a significant decrease in safety.

Each of the changes between the CTS and the ITS is classified into one of the following categories:

Administrative Chances (with a designator 'An) are changes to'the CTS that do not result in new requirements or change operational restrictions or flexibility. These changes are supported in aggregate by a single NSHC contained in Section V.

More Restrictive Chances (with a designator Mn) are changes to the CTS that establish a new requirement, require new or more frequent testing, or reduce operational flexibility. These changes are 4 supported in aggregate by a single NSHC contained in Section V.

Leis Restrictive Chances (with a designator Ln) are changes to the CTS that eliminate existing requirements, require less or less frequent testing, or increase operational flexibility. These changes are supported by a change specific NSHC contained in Part 3 of each subsection. )

Less Restrictive Administrative Chances (with a designator LAn and/or LBn) are changes to the CTS that relocate details out of the CTS and into the Bases. FSAR, or other appropriate licensee-controlled document. These are administrative changes because there is no change to the CTS requirement, it is siinply relocated to a licensee controlled document. These are less restrictive changes because the relocation results is a less restrictive change. control' process and a reduced level of regulatory oversight.

Part 3 consists'of the NYPA~ evaluations supporting a finding _of No Significant Hazards Considerations _ (NSHC) as re_ quired by 10 CFR 50.91(a)

' for proposed changes classified as Less Restrictive.

Attachment 1 JPN 99 008 Page 5 of 7 Part 4 consists of a copy of NUREG 1433, Revision 1, annotated to show differences between the Standard Technical Specifications and the proposed FitzPatrick ITS. These markups include cross references to the equivalent FitzPatrick CTS in Part 1 and cross references to the descriptims and justifications of the changes included in Part 2.

Cross refe ences to the Justifications for Differences between NUREG-1433 and the JAF ITS contained in Part 5 are also annotated.

Part 5 includes the Justification for Differences (JFDs) between NUREG-1433 and the FitzPatrick ITS. The FitzPatrick ITS differs from NUREG-1433 Revision 1, for any of the following reasons:

Existing requirements (Current Licensing Basis) are maintained where a need exists and the CTS requirement was previously justified and approved. Each of these changes was evaluated to ensure that the need still exists and that maintaining the CLB does not result in a significant' adverse impact on safety.

Plant-specific wording preferences or minor editorial improvements were incorporated into the Bases to improve clarity, or ensure  ;

requirements are fully understood and consistently applied by the NYPA staff.

Plant-specific difference in the design or design basis were incorporated as necessary to more precisely describe JAFNPP current design or practice.

Differences based upon a Generic Change Traveler for NUREG 1433, Revision 1 were incorporated.

Part 6 includes a copy of NUREG 1433, Revision 1. anncted to show the differences between the Bases for the STS and the proposed JAFNPP ITS Bases. These markups include cross reference to the Justification for Differences between NUREG 1433 and the JAFNPP ITS, which are contained in Part 7.

Part 7 includes the Justification for Differences (JFDs) i>etween NUREG-1433 and the JAFNPP ITS Bases. Differences between the NUREG 1433 Bases.

and the JAFNPP ITS Bases reflect the difference between the STS and the ITS as described in Part 5.

Part 8 is a typed fina' copy of the proposed FitzPatrick Improved Technical Specification including the associated Bases.

Attachment 1 JPN 99 008 Page 6'of-7 SECTION V. Evaluations supporting a finding of No Significant Hazards Considerations (NSHC) classified as Administrative, More Restrictive, Removed Detail or Relocated.

This Section consists of the NYPA evaluations supporting a' finding of No Significant Hazards Considerations (NSHC) as required by 10 CFR 50.91(a) for proposed changes classified as Administrative, More Restrit:tive, Removed Detail or Relocated.Section V also contains the environmental assessment in accordance with 10 CFR 51.21.

i 1

1 I

i

Attachment 1 JPN 99 008 Page 7 of 7-Table of Contents-The five sections, discussed previously, are contained in 19 volumes. _ A Table of Contents for these volumes is provided below.

VOLUME # SECTION # IIILE 1 I COVER LETTER &

SPLIT REPORT 2 II ITS SPECS 3 II ITS BASES (2.0 through 3.3) 4 II ITS BASES (3.3 through 3.10) 5 III CTS MARKUPS 6 IV .ITS 1.0, 2.0. 3.0 7 IV ITS 3.1 & 3.2 8 IV ITS 3.3.1 thru 3.3.4 9 IV ITS 3.3.5 thru 3.3.6.1 10 IV ITS 3.3.6.2 thru 3.3.8 11 IV ITS 3.4 12 IV ITS 3.5 13 IV ITS 3.6.1.1 thru 3.6.1.9 14 IV ITS 3.6.2.1 thru 3.6.4.3 15 IV ITS 3.7 thru 3.8.2 16 IV ITS 3.8.3 thru 3.8.8 17 IV ITS 3.9 18 IV ITS 3.10 & 4.0 19 IV ITS 5.0, CTS 6.0. CTS RETS, 19 V Generic NSHCs and Environmental Assessment

ATTACHMENT 2 TO JPN-99-008

)

List of the JAFNPP ITS Conversion Packages 1

-1

TABLE OF CONTENTS - IMPROVED TECHNICAL SPECIFICATIONS Page 1 of 4 Spec / Bases Volume Section Page # #

1.0 USE AND APPLICATION 1.1 Definitions.................................................. 1.1 1 6 1.2 Logi cal Connectors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1. 2 1 6 1.3 Completion Times............................................. 1.3 1 6 1.4 Frequency .................................................. 1.4 1 6 2.0 SAFETY LIMITS (SLs) 2.1.1 Reactor Core SLs......................................s...... 2.0 1 6 2.1.2 Reactor Coolant System (RCS) Pressure SL . . . . . . . . . . . . . . . . . . . . . 2.0-6 6 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY............. 3.0 1 6 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY...................... 3.0 4 6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)........................................ 3.1-1 7 3.1.2 Reactivity Anomalies......................................... 3.1 8 7 3.1.3 Control Rod OPERABILITY...................................... 3.1 13 7 3.1.4 Control Rod Scram Times...................................... 3.1-22 7 3.1.5 Control Rod Scram Accumulatort ............................... 3.1 29 7 3.1.6 Rod Pattern Control.......................................... 3.1 34 7 3.1.7 Standby Liquid Control (SLC) System.......................... 3.1 39 7 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves.......... 3.1 46 7 3.2 POWER DISTRIBUTION LIMITS 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE f

(APLHGR) ................................................ 3.2 1 7 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR).......................... 3.2-5 7 3.2.3 LINEAR HEAT GENERATION RATE (UiGR)........... ..... ... .... 3.2-10 7 3.2.4 Average Power Range Monitor (APRM) Gain and Setpoint ................................................ 3.2-13 7 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation.............. 3.3 1 8 3.3.1.2 Sourcc Range Monitor (SRM) Instrumentation. . . . . . . . . . . . . . . . . . 3.3 35 8 3.3.2.1 Control Rod Block Instrumentation............................ 3.3 44 8 3.3.2.2 Feedwater and Main Turbine High Water Level Trip Instrumentation ......................................... 3.3 57 8 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation........... ... 3.3-65 8 3.3.3.2 Remote Shutdown System....................................... 3.3 80 8 3.3.4.1 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS RPT) Instrumentation .................... 3.3-86 8 3.3.5.1 Emergency Core Cooling System (ECCS)

Instrumentation.......................................... 3.3 96 9 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation ......................................... 3.3 135 9 3.3.6.1 Primary Containment Isolation Instrumentation................ 3.3 147 9 3.3.6.2 Secondary Containment Isolation Instrumentation.............. 3.3 182 10 3.3.7.1 Control Room Emergency Ventilation Air Supply (CREVAS) System Instrumentation ......................... 3.3 193 10 3.3.7.2 Condenser Air Removal Pump Isolation Instrumentation ......................................... 3.3-198 10 3.3.7.3 Emergency Service Water (ESW) System Instrumentation ......................................... 3.3 205 10 3.3.8.1 Loss of Power (LOP) Instrumentation. . . . . . . . . . . . . . . . . . . . . . . . . . 3.3 211 10 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring .............................................. 3.3 218 10 2

TABLE OF CONTENTS - IMPROVED TECHNICAL SPECIFICATIONS Page 2 of 4 Section Spec / Bases Volume

  1. Paae #- #

3 73 INSTRUMENTATION (Continued)

N3.3.4.1 End of Cycle Recirculation Pump Trip (E0C RPT) Instrumentation.................................. Deleted 10 N3.3.6.3 Low Low Set (LLS) Instrumentation............................. Deleted 10 3.4 REACTOR COOLANT SYSTEM OCS) 3.4.1 Recirculation Loops 0perating................................ 3.4 1 11 3.4.2 Jet Pumps.................................................... 3.4 9 11 3.4.3 Safety / Relief Valves (S/RVs) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4 14 11 3.4.4 RCS Operati onal LEAKAGE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 4 19 11 3.4.5 RCS Leakage Detection Instrumentation................ ....... 3.4 25 11 3.4.6 RCS Specific Activity. . . . . . . ............................... 3.4 31 11 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System Hot Shutdown ..................................... 3.4 35 11 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System Cold Shutdown .................................... 3.4 40 11 3.4.9 RCS Pressure and Temperature (P/T) Limits.................... 3.4 45 11 N3.4.5 RCS Pressure Isolation Valve (PIV) Leakage................... Delf:ted 11 N3.4.11 Reactor Steam Dome Pressure. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Del ated 11 CTS 3/4.6.F Structural Integri ty . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Rel ocated 11 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS 0 )e ra ti ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 . 5 1 12 3.5.2 ECCS 51ut down . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 . 5 20 12 3.5.3 RCIC System.................................................. 3.5-26 12 3.6 CONTAINMENT SYSTEMS 3.6.1.1 Pri ma ry Co nt a i nment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.6 1 13 3.6.1.2 Primary Containment Air Locks................................ 3.6 6 13 3.6.1.3 Primary Containment Isolation Valves (PCIVs) . . . . . . ......... 3.6 14 13 3.6.1.4 Drywel l Pres sure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 6 29 13 3.6.1.5 Drywell Air Temperature...................................... 3.6 32 13 3.6.1.6 Reactor Building to Suppression Chamber Vacuum Breaker 3.................................................. 3.6 35 13 3.6.1.7 Suppression Chamber to Drywell Vacuum Brealcers. . . . . . . . . . . . . . 3.6-42 13 3.6.1.8 Main Steam Leakage Collection (MSLC) System.................. 3.6 48 13 3.6.1.9 Residual Heat Removal (RHR) Containment Spray System.............................................. 3.6 52 13 3.6.2.1 Suppression Pool Average Temperature......................... 3.6 57 14 3.6.2.2 Suppression Pool Water Level................................. 3.6 63 14 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Coo l i ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 . 6 - 67 14 3.6.2.4 Drywell to Suppression Chamber Differential Pressure.................................................. 3.6 72 14 3.6.3.1 Primary Containment Oxygen Concentration..................... 3.6 76 14 3.6.3.2 Containment Atmosphere Dilution (CAD) System................. 3.6 79 14 3.6.4.1 Secondary Cont ai nment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 6 - 84 14 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)............... 3.6-90 14 3

TABLE OF CONTENTS - IMPROVED TECHNICAL SPECIFICATIONS Page 3 of 4 Section Spec / Bases Volume

  1. Paae # #

3.6 CONTAINMENT SYSTEMS (continued) 3.6.4.3 Standby Gas Treatment (SGT) System........................... 3.6 97 14 N3.6.1.6 Low Low Set (LLS) Valves................ ..................... Deleted 14 N3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Del et ed 14 N3.6.3.1 Primary Containment Hydrogen Recomb 1ners...................... Deleted 14 N3.6.3.2 Drywell Cool i ng System Fans . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Del eted 14 CTS 3.7.A.3 Containment Purge through the Standby Gas Treatment System........................................... Relocated 14 3.7 PLANT SYSTEMS 3.7.1 Residual Heat Removal Service Water (RHRSW) System 3.7-1 3.7.2 Emergency Service Water (ESW)] System and Ultimate Heat Sink (UHS) ......................................... 3.7 7 15 3.7.3 Control Room Emergency Ventilation Air Supply (CREVAS) System ......................................... 3.7-15 15 3.7.4 Control Room Air Conditioning (AC) System.................... 3.7 22 15 3.7.5 Main Condenser Steam Jet Air Ejector (SJAE)

O f fg a s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 . 7 28 15 3.7.6 Main Turbine Bypass System................................... 3.7 32 15 3.7.7 Spent Fuel Storage Pool Water Level . . . . . . . . . . . . . . . . . . . . . . . . . 3.7-37 15 N3.7.3 Diesel Generator (DG) (1B) Stanby Service Water (SSW) System ....................................... Deleted 15 CTS 3/4.8 Miscellaneous Radioactive Material s Sources . . . . . . . . . . . . . . . . . . . Relocated 15 CTS 3/4.11.C Battery Room Ventil ation. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Rel ocated 15 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources - Operating....................................... 3.8 1 15 3.8.2 AC Sources - Shutdown.................................. ..... 3.8-29 15 3.8.3 Diesel Fuel Oil, Lube 011. and Starting Air........ ......... 3.8-35 16 3.8.4 DC Sources Operating.............................. ........ 3.8-45 16 3.8.5 DC Sources Shutdown........................................ 3.8-54 16 3.8.6 Battery Cell Parameters . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.8 58 16 3.8.7 Distribution Systems - Operating............................. 3.8-65 16

{

3.8.8 Distribution Systems - Shutdown.............................. 3.8 74 16 N3.8.7 Inverters 0perati ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . Del eted 16 N3.8.8 Inverters Shutdown............................................ Deleted 16 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.9 1 17 3.9.2 Refuel Position One Rod Out Interlock. . . . . . . . . . . . . . . . . . . . . . . . 3.9 6 17 3.9.3 Control Rod Position......................................... 3.9 10 17 3.9.4 Control Rod Position Indication. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.9 13 17 3.9.5 Control Rod OPER/.BILITY Refueling. . . . . . . . . . . . . . . . . . . . . . . . . 3.9 17 17 3.9.6 Reactor Pressure Vessel (RPV)] Water Level . . . . . . . . . . . . . . . . . . . 3.9 20 17 3.9.7 Residual Heat Removal (RHR) High Water Level....... ..... . 3.9 23 17 3.9.8 Residual Heat Removal (RHR) Low Water Level . . . . . . . . . . . . . . . . 3.9 27 17 N3.9.7 Reactor Pressure Vessel (RPV) Water Level New Fuel or Control Rods . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Deleted 17 4

l

- _ _ _ _ _ _ _ _ _ _ _ - _--___a

TABLE OF CONTENTS IMPROVED TECHNICAL SPECIFICATIONS Page 4 of 4 Section Spec / Bases Volume

  1. Pace # #

3.10 SPECIAL OPERATIONS 3.10.1 Inservice Leak and Hydrostatic Testing Operation............. 3.10 1 18 3.10.2 Reactor Mode Switch Interlock Testing. . . . . . . . . . . . . . . . . . . . . . . . 3.10 6 18 3.10.3 Single Control Rod Withdrawal Hot Shutdown. . . . . . . . . . . . . . . . . 3.10 11 18 3.10.4 Single Control Rod Withdrawal Cold Shutdown................. 3.10 16 18 3.10.5 Single Control Rod Drive (CRD)

Removal Refueli ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.10 21 18 3.10.6 Mul tiple Control Rod Withdrawal - Refue11ng. . . . . . . . . . . . . . . . . . 3.10 26 18 3.10 7 Control Rod Testing - Operating.............................. 3.10 30 18 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling....................... 3.10 34 18 N3.10.9 Reci rcul ation Loops Testi ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Del eted 18 N3.10.10 Training Startups............................................. Deleted 18 4.0 DESIGN FEATURES 4.1 Site Location................................................ 4.0 1 18 4.2 Reactor Core................................................. 4.0 1 18 4.3 Fuel Storage................................................. 4.0 2 18 5.0 ADMINISTRATIVE CONTROLS 5.1 Re sponsi bi l i ty . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5. 0 1 19 5.2 0rganizatica................................................. 5.0 2 19 5.3 Pl ant Sta ff Quali fi cations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5. 0 4 19 5.4 Procedures................................................... 5.0 5 19 5.5 Programs and Manua1.......................................... 5.0 6 19 5.6 Reporting Requirements....................................... 5.0 19 19 5.7 High Radiation Area........................................... 5.0 23 19 CTS 6.0 Admi ni strat i ve Cont rol s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 CTS RETS 2.1 Li qui d E f fl uent Moni to rs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 2.2 Concentration of Liquid Effluents . . . . . . . . . . . . . . . . . . . . . . . . 19 2.3 Dose From Li qui d E f fl uents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 2.4 Liquid Radioactive Waste Treatment System................ 19 3.1 Gaseous Ef fl uent Moni tors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 3.2 Gaseous Dose Rate......................................... 19 3.3 Air Dose. Noble Gas ..................................... 19 3.4 Dose Due to Iodine 131. Iodine I33. Tritium and Radionuclides in Particulate Form . . . . . . . . . . . . . . . . . 19 3.6 Offgas Treatment System ................................. 19 4.0 Solid Radioactive Waste...... ........................... 19 5.0 Total Dose............................................... 19 6.1 Honi tori ng Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 6.2 Land Use Census Program.................................. 19 6.3 Interlaboratory Comparison Program....................... 19 Generic Changes No Significant Hazards Considerations . . . . . . . . . . . . . . . . . . . . 19 5

ATTACHMENT 3 TO JPN-99-008 List of JAFNPP Pending License Amendment Requests

-(JPTSs)

Attachment 3 JPN 99 008 Page 1 of 1 TAC NP N NYPA JPTS JPTS Title Number and ) ate Number H99751 JPN 97 032 JPTS97-004 Distribution of Inoperable Control Rods 10/08/97 MA1136 JgN;98;gg7 JPTS 97-007 Revision to SGT Charcoal Efficiency and Change for Increasing Allowable Containment Leakage (L.)

M94611 J g g g4 JPTS 95 007 Emergency Diesel Generator Allowable Out-of service Time JPN 96 018 Response to written Request for Additional 04/26/96 Information dated 4/18/96 JPN 96 038 Response to verbal Request for Additional 09/12/96 Information dated 6/17/96 Jgg2 Response to written Request for Additional Information dated 2/4/97 JPN 97 027 Response to verbal Request for Additional 09/09/97 Information dated 9/3/97 M95521 JgN;9g;gg3 JPTS 95 005 Fire Protection Procedure' Review MA2131 Jg8g6 JPTS 98 001 SRC Review and Audit Requirements

ATTACHMENT 4 TO JPN-99-008 Improved Standard Technical Specification Change Travelers l

I f

)

Attachment 4 JPN 99 008 GENERIC CHANGE TRAVELERS INCORPORATED INTO ITS SUBMITTAL Revision l Traveler (Approved, Related )

(TSTF) except as Description ITS i

, Lumber noted) Sections TSTF-002 1 Relocate the 10 year sediment cleaning of the 3.8.3 fuel oil storage tank to licensee control TSTF-005 1 Delete safety limit violation notification 2.0 l requirements TSTF-008 2 Revise the SR 3.0.1 Bases to allow credit for 3.0 unplanned events to meet any Surveillance 3.8.1 3.8.4 TSTF-009 1 Relocate value for shutdown margin to COLR 3.1.1 TSTF-017 1 Extension of testing frequency of containment 3.6.1.2 airlock interlock mechanism from 184 days to 24 months TSTF-018 1 Require only one (secondary) containment 3.6.4.1 access door per access opening to be closed TSTF-030 2 Extend the Completion Time for inoperable 3.6.1.3 isolation valve to a closed system to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> TSTF-032 0 Slow / Stuck Control Rod Separation Criteria 3.1.3 TSTF-033 0 Specification 3.1.3 Required Action A.2 3.1.3 Completion Time TSTF-034 0 Delete Requirements to Disarm the associated 3.1.3 CRD when two or more withdrawn control rods are stuck TSTF-035 0 Recirculation pump start RPV temperature 3.4.9 limits verification TSTF-036 3 Addition of LC0 3.0.3 N/A to shutdown 3.8.2.3.8.5 (Approval electrical power specifications 3.8.8 Pending)

TSTF-045 1 Exempt verification of CIVs that are not 3.6.1.3 locked, sealed or otherwise secured TSTF-046 1 Clarify the CIV surveillance to apply only to 3.6.4.2 automatic isolation valves 3.6.1.3 TSTF-065 1 Use of generic titles for utility positions 2.0 l 5.0 TSTF-071 2 Add example of SFDP to the 3.0.6 Bases 3.0

Attachment 4 JPN 99 008 Revision Traveler (Approved, Related (TSTF) 'except as Description .ITS' Number noted) Sections TSTF-086 0 Delete overtime requirements in,- 5.0 (Approval Section 5.0 Pending)

TSTF-106 1 Change to Diesel Fuel Oil Testing Program 5.0 TSTF-139 1 Incorrect Criteria Defined in B 3.7.1.6 3.7.7 TSTf-163 2 Minimum vs. Steady State Voltage and 3.8.1 Frequency TSTF-202 0 Revise battery Surveillance weekly 3.8.4 3.8.6 Frequencies TSTF-221 0 Delete Incorrect 3.10.8 Condition C 3.10.8 TSTF-225 0 Fuel movement with inoperable refueling 3.9.1 equipment interlocks TSTF-229 0 Revise SR 3.2.2.2 for consistency with 3.2.2 (Approval SR 3.1.4.4 Pending)

TSTF-232 0 Refuel Equipment Interlocks Applicability 3.9.1 (Approval Change l Pending)

Attrchment 5 JPN-99-008 ATTACHMENT 5 to JPN-99-008 Changes Beyond Conversion

& Beyond CTS Retention 4

Attachment 5 JPN-99-008 Changes Beyond Conversion

& Beyond CTS Retention

1. Several LSFTs changed to 24 month frequency
2. MSIV closure scram reduced to less than equal to 14 %
3. ECCS flowrates reduced to SAFER /GESTR LOCA values
4. DC Sources - Operating changed to-allow a 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> completion time for the restoration of an inoperable subsystem before requiring plant shutdown
5. AC Sources - Operating changed to allow a 36 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Completion Time for power reduction (to less than or equal to 45%) following loss of two reserve circuits
6. ITS 3.0.3 changed to allow 9 hour1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> Completion Time to be in Mode 3 (other shutdown completion times changed as well)

Attechmint 6 JPN-99-OO8 ATTACHMENT 6 to JPN-99-008 List of Commitments

Attachm:nt 6

. JPN-99-008 Attachment 6 LIST OF COMMITMENTS Commitment No. Description Due Date JPN-99-008-01 Supplement the ITS Coriversion June.1,1999 Packages to reflect the withdrawal of the proposed license amendment for Inservice Leak and Hydrostatic Testing.

JPN-99-008-02 Provide a date for completion of April 14,1999 calculations for all Allowable Values, JPN-99-008-03 Provide a date for the implementation April 14,1999 of the improved Technical Specifications.

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