ML20236M623
| ML20236M623 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/10/1998 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20236M609 | List: |
| References | |
| NUDOCS 9807140165 | |
| Download: ML20236M623 (24) | |
Text
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.. . e l Attichment I to JPN-98-029 PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES (JPTS-98-004) l (NOTE: Proposed changes to the Technical Specifications are shown by a bar in the right hand margin) t i-i l
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l New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59 9007140165 900710 l PDR ADOCK 05000333 4 P PDR &
JAFNPP TABLE OF CONTENTS (Cont'd)
Ea92
. F. , ECCS-Cold Condition F. 122 G. Maintenance of Filled Discharge Pipe G. 122a H. Average Planar Linear Heat Generation Rate H. 123 (APLHGR)
- 1. Linear Heat Generation Rate (LHGR) 1. 124 J. Thermal Hydraulic Stability DELETED 124a K. Single-Loop Operation NONE 124a SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REQUIREMENTS 3.6 Reactor Coolant System 4.6 136 A. Pressurization and Thermal Limits A. 130 B. DELETED C. Specific Activity C. 139 l D. Coolant Leakage D. 141 E. Safety and Safety / Relief Valves E. 142a F. Structural integrity F. 144 G. Jet Pumps G. 144 H. DELETED
- 1. Shock Suppressors (Snubbers) 1. 145b 3.7 Containment Systems 4.7 165 A. Primary Containment A. 165 B. Standby Gas Treatment System B. 181 C. Secondary Containment C. 184 D. Primary Containment isolation Valves D. 185 3.8 Miscellaneous Radioactive Material Sources 4.8 214 3.9 Auxiliary Electrical Systems 4.9 215 A. Normal and Reserve AC Power Systems A. 215 B. Emergency AC Power System B. 216 C. Diesel Fuel C. 218 D. Diesel-Generator Operability D. 220 E. Station Batteries E. 221 F. LPCI MOV Independent Power Supplies F. 222a G. Reactor Protection System Electrical Protection G. 222c Assemblies 3.10 Core Alterations 4.10 227 A. Refueling Interlocks A. 227 B. Core Monitoring B. 230 C. Spent Fuel Storage Pool Water Level C. 231 D. Control Rod and Control Rod Drive Maintenance D. 231 3.11 Additional Safety Related Plant Capabilities 4.11 237 A. Main Control Room Ventilation A. 237 B. DELETED C. Battery Room Ventilation C. 239 i
l Amendment No. 20,40,00,110,100,201,200, ii
JAFNPP LIST OF FIGURES Figures litig Eggg ,
1
-4.1-1 (Deleted) 4.2-1 (Deleted) 3.4-1 Sodium Pentaborate Solution (Minimum 34.7 B-10 Atom % Enriched) 110 Volume-Concentration Requirements 3.4-2 Saturation Temperature of Enriched Sodium Pentaborate Solution 111 3.5-1 (Deleted) ,
3.6-1 Reactor Vessel Pressure - Temperature Limits Through 12 EFPY 163- I Part 1 3.6-1 Reactor Vessel Pressure - Temperature Limits Through 14 EFPY 163a Part 2 -
3.6-1 Reactor Vessel Pressure - Temperature Limits Through 16 EFPY 163b Part 3 4.6-1 (Deleted) l
'6.1-1 (Deleted) I l
6.2-1 (Deleted) l l
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Attachment ll to JPN-98-029 i
SAFETY EVALUATION FOR PROPOSED TECHNICAL SPECIFICATION CHANGES (JPTS-98-OQ41 i
l
)
l l
l l
New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59 l
l
i l
l Attichm:nt Il to JPN-98-029 F. .
SAFETY EVALUATION Page 1 of 4 4
- 1. DESCRIPTION OF THE PROPOSED CHANGES This amendment proposes to delete reactor coolant chemistry specifications for reactor coolant conductivity and chloride concentration from the Technical Specifications.
- 1. DESCRIPTION OF THE PROPOSED CHANGES TO THE TS Technical Specifications Paae ii. Table of contents l Replace the following:
"C. Coolant Chemistry C. 139" with "C. Specific Activity C. 139" Technical Specifications Paae vii. List of Fioures Replace the following:
"4.6-1 Chloride Stress Corrosion Test Results at 500*F 164" with "4.6-1 (DELETED)"
Technical Specifications Paae 139
, Replace the following for 3/4.6.C:
"C. Coolant Chemistrv" with "C Soecific Activitv" Technical Specifications Paaes 140 and 141 Delete the Technical Specification Limiting Conditions for Operations and Surveillance Requirements Sections 3.6.C.2,3,4 and 5 and 4.6.C.2 and 3.
Technical Specifications Paae 149 Replace the following:
"C. Coolant Chemistry" with "C. Specific Activity"
7_
Att: chm:nt ll to JPN-98-029 i SAFETY EVALUATION Page 2 of 4 l
l Delete the Following:
Delete the last 5 paragraphs on page 149 of TS Bases Section 3/4.6.C Technical Specifications Pace 150 Delete the Following:
1 Delete the 4 paragraphs on page 150 for TS Bases Section 3/4.6.C Technical Specifications Pace 164 Remove Figure 4.6-1 and replace with
"(This page intentionally left blank)"
- 2. DESCRIPTION OF THE PROPOSED CHANGES TO THE UFSAR l
Paragraphs discussing reactor coolant chemistry conductivity and chloride concentration will be added to UFSAR Section 16, " Appendices". The reactor coolant chemistry conductivity and chloride concentration limits and a basis discussion will be sufficiently described in the FSAR to ensure that changes to these limits are performed in accordance with 10 CFR 50.59.
- 3. DESCRIPTION OF THE PROPOSED CHANGES TO FITZPATRICK ADMINISTRATIVE PROCEDURE AP-01.04 FitzPatrick Administrative Procedure AP-01.04, " Tech Spec Related Requirements, Lists, and Tables", will be revised to contain the Reactor Coolant System - Coolant Chemistry Limiting Conditions for Operation, Surveillance Requirements, and Bases for coolant conductivity and chloride concentration currently contained in the Technical Specifications, ll. PURPOSE OF THE PROPOSED CHANGES The proposed amendment will relocate portions of the " Reactor Coolant System - Coolant Chemistry" specification 3/4.6.C. from the Technical Specifications to the James A.
FitzPatrick Updated Final Safety Analysis Report (UFSAR) and to applicable plant procedures that are controlled by the 10 CFR 50.59 process. The Technical Specifications )'
for " Coolant Chemistry" contain specifications for reactor coolant specific activity, 1-conductivity, and chloride concentration. This amendment will relocate the specifications for reactor coolant conductivity and chloride concentration and retain the specification for '
reactor coolant specific activity.
l 111. SAFETY IMPLICATIONS OF THE PROPOSED CHANGES l
t The Commissions Final Policy Statement on Technical Specification improvements for Nuclear Power Reactors (Reference 1) concluded that the purpose of the Technical Specifications is to impose those conditions or limitations upon reactor operations necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety. The Policy Statement recommends that TS that do not meet the screening criteria for retention as a TS may be relocated to
Att: chm:nt 11 to JPN-98-029 SAFETY EVALUATION Page 3 cf 4 l
another licensee controlled document. The reactor cot,! ant chemistry TS that are proposed to be relocated do not meet the screening criteria of 10 CFR 50.36 and do not constitute
! performance requirements necessars; to ensure safe operation of the facility and therefore do not warrant being in the TS.
The proposed changes are administrative in nature since the requireinents of the relocated i TS will not be changed at the time; of relocation.
IV. EVALUATION OF SIGNIFICANT HAZANOS CONSIDERATION The Commission has provided standards (10 CFH Cection 50.92(cR for determining whether a significant hazards consideration exists. A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not (1) involve a sign;ficant increase in the probability or consequences of an accident previously evaluated; (2) create the possibility of a new or different kind of accident from any accident previously evaluateo; or (3) involve a significant reduction in a margin of safety.
After reviewing this proposed TS amendment, we have concluded:
- 1. The proposed TS amendment will not significantly increase the probability or consequences of any previously evaluated accidents.
The proposed changes simplify the TS, meet regulatory requirements for relocated TS, and implement the recommendations of the Commission's Final Policy Statement on TS improvements. Future changes to these requirements will be controlled by 10 CFR 50.59. The proposed changes are administrative in nature and do not involve any modification to any plant equipment or affect plant operation.
Therefore, the proposed changes do not involve a significant increase in the probability or consequences of any previously evaluated accident.
- 2. The proposed TS amendment will not create the possibility of a new or different kind of accident.
The proposed changes are administrative in nature, do not involve any physical alterations to any plant equipment, and cause no change in the method by whi.:h any safety related system performs its function. Therefore, this proposed TS amendment will not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. The proposed TS amendment will not involve a significant reduction in a margin of safety.
The proposed changes are administrative in nature, will not alter the basic regulatory requirements, and do not affect any safety analyses. Therefore, no margin of safety is reduced as a result of these changes.
Based on the above, we have determined that the proposed TS amendment will not involve a significant hazards consideration.
f l
l
Att chm:nt 11 to JPN-98-029 i
. SAFETY EVALUATION Page 4 of 4 V. IMPLEMENTATION OF THE PROPOSED CHANGES Implementation of the proposed changes will not adversely affect the ALARA or Fire Protection Programs at the FitzPatrick plant, nor will the changes affect the environment.
implementation of this Amendment requires changes to the FitzPatrick Final Safety Analysis Report and to a FitzPatrick Administrative Procedure AP-01.04, " Tech Spec Related Requirements, Lists, and Tables." These changes are described in section I of the safety evaluation VI. CDNCLUSION The incorporation of these changes: a) will not increase the probability nor the consequences of an accident or malfunction of equipment important to safety as previously evaluated in the Safety Analysis Report; b) will not increase the possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report; c) will not reduce the margin of safety as defined in the bases for any technical specification; d) does not constitute an unreviewed safety question; and e) involves no significant hazards considerations as defined in 10 CFR 50.92.
Vll. REFERENCES
- 1. NRC Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated 7/22/93.
i 7
l -
Attachment 111 to JPN-98-029 MARKUP OF TECHNICAL SPECIFICATION PAGES (JPTS-98-OO4) l l
l New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59
JAFNPP Ilb2LE OF CONTENTS (Cont'd)
Eaan
' F. ECCS-Cold Cor.dition F. 122 G. Maintenance, of Filled Discharge Pipe G. 1.22a H. Average Planar Linear Heat Generation' Rate H. 123 (APLHGR) 1.
J.
Linear Heat 3eneration Rate (LHGM)
Thermal Hydraulic Stability 1.
DELETED 124 124a A K. Single Loop Operation NONE 124a /
SURVEILLANCE LIMITING CONDITIONS FQR C*ERATION REQUIREMEliTj, 3.6 Reactor Coolant System 4.6 136 A. Pressurization and Thermal Limits A. 136 B. DELETED C.-C 9
- Ch ...e;;I5p l(.i 643y l C. 139 (
i D. Coolant Leakage D. 141 l E. Safety and Safety / Relief Valves E. 142a
! F. Structural integrity F. 144 G. Jet Pumps G. 144 H. DELETED
- 1. Shock Suppressors (Snubbers) 1. 145b l 3.7 Containment Systems 4.7 165 A. Primary Containment A. 165 i B. Standby Gas Treatment System -
B. 181 184 C. Secondary Containment . C.
D. Primary Containment laolation Valves 185 D.
i . 3.8 Miscellaneous Radioactive Meterial Sources 4.8 214 3.9 Auxiliary Electrical Systema 4.9 215 l
A. Normal and Reserve AC Power Systems A. 215
- 8. Emergency AC Power System B. 216 C. Diesel Fuel C. 218 D. Diesel-Generator Operability D. 220 E. Station Betteries E. 221 F. LPCI MOV Independent Power Supplies F. 222a G. Reactor Protection System Electncal Protection G. 222c Assemblies 3.10 Core Alterations 4.10 227 A. Refueling interlocks A. 227 B. Core Monitoring B. 230 C. Spent Fuel Storage Pool Water Level C. 231 D. Control Rod and Control Rod Onve Maintenance D. 231 3.11 Addetional Safety Related Plant Capabilities 4.11 237 A. Main Control Room Ventdation A. 237 B. DELETED C. Battery Room Ventilation C. 239 f
Amendment No. 20. i!, SS,
- t 3, t !!, 2?? -296-I
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f . J4FNPP
. . LIST OF FIGURES famEa1 T.itla' Eaan 4.1 1 (Deleted) 4.21 (Deleted) 3.4-1 Sodit.m Pentaborate Sc!ution (Mmimum 34.7 B-10 Atom % Enriched) 110 Volume-Concentration Requirements 3.4-2 Saturation Temperature of Enriched Sodium Pentaborate Solution 111 [
3.5-1 (Deleted) 3.6-1 Reactor Vessel Pressure - Temperature Limits Through 12 EFPY 163 l Part 1 3.6-1 Reactor Vessel Pressure - Temperature Limits Through 14 EFPY 163a Part 2 3.6-1 Reactor Vessel Pressure - Temperature Limits Through 16 EFPY 163b Part 3 g ..
4.6-1 !- " *^---- *~ -I That-60(Pfd, ygg(l) '@9) l 6.1-1 (Deleted) l 6.2-1 (Deletad) l i
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Amendment No. . 22, '?, I', 72, 7', SS, OS.
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! e l l JAFNPP Attachment IV to JPN-98-029 l
SUMMARY
OF COMMITMENTS (JPTS-98-004) l Number Commitment Due Date 1 ! JPN-98-029-01 The operability and surveillance requirements for reactor 30 days coolant chemistry conductivity and chloride concentration will from NRC l be relocated to an Authority controlled prc;edure. approval of l TSA l JPN-98-029-02 The operability and surveillance requirements for reactor 1999 FSAR l coolant chemistry conductivity and chloride concentration will update be sufficiently described in the FSAR to ensure that future (May 1999) changes to these requirements will be controlled under the provisions of 10 CFR 50.59. i l l l I r I l l e--- - - - - _ _ _ - - - - _ - - - --_ - - - - - - - - - - - - - - - - -- _ ----_- - - - - - - - - - - - - - - - - - - - - - - _ - - _------------_-------;}}