ML20212L107
| ML20212L107 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  (NPF-86-A-063) |
| Issue date: | 10/01/1999 |
| From: | Clifford J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20212L111 | List: |
| References | |
| NUDOCS 9910070161 | |
| Download: ML20212L107 (10) | |
Text
i
[
4 UNITED STATES NUCLEAR REGULATORY COMMISSION 3
WASHINGTON, D.C. 20EH001
\\..... /
NORTH ATLANTIC ENERGY SERVICE CORPORATION. ET At
- DOCKET NO. 50-443 SEABROOK STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATC - L LICENSE Amendment No. 63 License No. NPF-86 i
1.
The Nuclear Regulatory Commission (the Commission) has found that:
I A.
The application for amendment filed by the North Atlantic Energy Service Corporation, et al. (the licensee), dated December 16,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act,
)
and the rules and regulations of the Commission; 1
C.
There is reasonable assurance (i) that the activities authorized by this amendment i
can be conducted without endangering the health and safoty of the public, and (ii) that
)
such activities will be conducted la compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- North Atlantic Energy Service Corporation (NAESCO) is authorized to act as agent for the:
North Atlantic Energy Corporation, Canal Electric Company The Connecticut Light and Power
- Company, Great Bay Power Corporation, Hudson Light & Power Department, Massachusetts Municipal Wholesale Electric Company, Montaup Electric Company, New England Power Company, New Hampshire Electric Cooperative, Inc., Taunton Municipal Light Plant, The 1
United illuminating Company, and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
9910070161 991001 PDR ADOCK 05000443 P
FDR
9 9 l l
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-86 is hereby amended to read as follows:
(2) Technical Soecifications l
The Technical Specifications contained in Appendix A, as revised through Amendment No.63 and the Environmental Protection Plan contained in Appendix B are incorporated into Facility License No. NPF-86. NAESCO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance, to be implemented within 90 days of issuance, including relocation of requirements to the Seabrook Station Technical Requirements Manual.
FOR THE NUCLEAR REGULATORY COMMISSION Afh J
es W. Clifford, Chie, Section 2 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 1,199'i l
l l
l '
p t!.
I' ATTACHMENT TO LICENSE AMENDMENT NO. 63 FACILITY OPERATING LICENSE NO. NPF-86 DOCKET NO. 50-443 Replace the following pages of the Appendix A, Technical Specifications, with the attached revised pages as indicated. The revised pages are identified by amendment number and contain marginallines indicating the areas of change. Overleaf pages have been provided.*
Remove Insert vii*
vii' viii viii I
xi xi xii*
xii' 3/4 7-23 3/4 7-23 3/4 7-24 3/4 7-24
- B 3/4 7-5 B 3/4 7-5 I
l L'
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS P
SECTION PAGE Contai nment Ai r Loc ks....................................
3/4 64 Internal Pressure........................................
3/4 6-9 A i r Tempe ra t ure..........................................
3/4 6-10 Containment Vessel Structural Integrity..................
3/4 6-11 Containment Ventilation Systes...........................
3/4 6-12 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 4
Containment Spray System.................................
3/4 6-14 Spray Additive Systes........~............................
3/4 6-15 l
3/4.6.3 CONTAINMENT ISOLATION VALVES.............................
3/4 6-16 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Monitors........................................
3/4 6-18 Electric Hydrogen Recombiners............................
3/4 6-19 Hydrogen Mixing System...................................
3/4 6-20 1
3/4.6.5 CONTAINMENT ENCLOSURE BUILDING Containment Enclosure Emergency Air cleanup Systas.......
3/4 6-21 Containment Enclosure Building Integrity.................
3/4 6-24 Containment Enclosure Building Structural Integrity......
3/4 6-25 3/4.7 PLANT SYSTEMS I
3/4.7.1~ TURBINE CYCLE
- - ~ - --
Safety Va1ves............................................
3/4 7-1 TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH IN0PERA8LE STEAM LINE SAFETY VALVES DURING FO UR-LOO P 0P E RATI ON..............,.......................
3/4 7-2 TABLE 3.7-2 STEAM LINE SAFETY VALVES PFI L00P.....................
3/4 7-2 Auxi l i ary Feedwater-Sys tem...............................
3/4 7-3 Condensate Storage Tank..................................
3/4 7-6 Specific Activity........................................
3/4 7-7 TABLE 4.7-1 SECONDARY C00LANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM.....................................
3/4 7-8 Main Steam Line Isolation Va1ves.........................
3/4 7-9 Atmospheric Relief Valves................................
3/4 7-10 lL s
SEABD0K - UNIT 1 vii Amendment No. 14 UG 2 715o2
uwtm
~-
. LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE SECTION 3/4.7.2L STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION 3/4 7-11 3/4.7.3 PRIMARY COMPONENT COOLING WATER SYSTEM...
3/4 7-12 3/4 7-13 3/4.7.4 SERVICE WATER SYSTEM.........................................
3/4 7-14
'3/4.7.5 U LTI MATE H EAT S I N K................................................
3/4.7.6 CONTROL ROOM SUBSYSTEM '
3/4 7-16 Emergency Makeup Air and Filtration...............................
3/4 7-18a Ai r C ond itioning............................................................
3/4 7-19 3/4.7.7 SNUBBERS........................................................,,
3/4 7-20 3/4.7.8 SEALED SOURCE CONTAMINATION...........................
3/4 7-22 3/4.7.9 (THIS SPECIFICATION NUMBER IS NOT USED).................
3/4 7-23 3/4.7.10 (THIS SPECIFICATION NUMBER IS NOT USED)........
3/4 7-24 TABLE 3.7-3 '(THIS TABLE NUMBER IS NOT USED)....
3/4.8 ELECTRICAL" POWER SYSTEMS 3/4.8.1
- A.C. SOURCES 3/4 8-1 Operating........
3m 8-10 TABLE 4.8-1. (THIS TABLE NUMBER IS NOT USED)...............
3/4 8-11 S h u td ow n................................................................
3/4.8.2 D.C. SOURCES 3/4 8-12 Ope reting.................................
-TABLE 4.8-2 BATTERY SURVEILLANCE REQUIREMENTS.
3/4 8-14 3/4 8-15 S h u td ow n.......................................................
3/4.8.3 ONSITE POWER DISTRIBUTION 3/4 8-16 O pe rati ng.............................................
3/4 8-18
. S h utd ow n......................................................................
3/4 8-19 Trip Circuit for Inverter I-2A...........................................
3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES A.C. Circuits inside Primary Containment..............................
3/4 8-20
' Containment Penetration Conductor Overcurrent Protective Devices and Protective Devices for Class 1E Power Sources Connected to Non-Class 3/4 8-21 1 E C i rcu its...........................................,.................................
3/4 8-24 Motor-Operated Valves Thermal Overload Protection................
3/4.9 REFUELING OPERATIONS 3/4 9-1 3/4.9.1 BORON CONCENTRATION....................................
3/4 9-2 3/4.9.2 INSTRUMENTATION...............................
3/49-3 3/4.9.3 DECAY TIM E.........................
SEABROOK - UNIT 1 viii Amendment No. 56,5g,63
I.
INDEX BASES SECTION
_PAGE 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION.............
B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM...........
B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and STORAGE P00L............................................
B 3/4 9-2 3/4.9.12 FUEL STORAGE BUILDING EMERGENCY AIR CLEANING SYSTEM.......
B 3/4 9-2 3/4.9.13 SPENT FUEL ASSEMBLY ST0 RAGE..........................
B 3/4 9-3 3/4.9.14 NEW FUEL ASSEMBLY ST0 RAGE.................................
B 3/4 9-3 3/4.10 SPECD!. TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN...........................................
B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTI0M AND POWER DISTR 3/4.10.3 PHYSICS TESTS...........,.................IBUTION LIMITS....
B 3/4 10-1 B 3/4 10-1
^
3/4.10.4 REACTOR COOLANT L00PS...........................
B 3/4 10-1 3/4.10.5 POSITION INDICATION SYS(EM - SHUTD0WN...........
B 3/4 10-1 3/4.10. 6 REACTOR COO LANT L00PS....................................
B 3/4 10-1 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS..................................
B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS.................................
B 3/4 11-2 3/4.11.3 SOLID RADIOACTIVE WASTES..................
B 3/411-3/4.11.4 TOTAL D0SE...............................................
B 3/411-3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PR0 GRAM.......................................
B 3/4 12-1 3/4.12.2 LAND USE CENSUS..........................................
B 3/4 12-1 3/4.12.3 INTERLABORATORY COMPARISON PR0 GRAM.......................
B 3/4 12-2 5.0 DESIGN FEATURES 5.1 SITE 5.1.1 EXCLUSION AREA..............................................
5-1 5.1. 2 LOW POPULATION 20NE....i....................................
5-1 5.1.3 MAPS DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADI0 ACTIVE GASEOUS AND LIQUID EFFLUENTS....................
5-1 FIGURE 5.1-1 SITE AND EXCLUSION AREA B0VNDARY.....................
5-3 FIGURE 5.1-2 LOW POPULATION 20NE..................................
5-5 FIGURE 5.1-3 LIQUID EFFLUENT DISCHARGE LOCATION...................
5-7 5.2 CONTAINMENT 5.2.1 CONFIGURATION...............................................
5-1 5.2.2 DESIGN PRESSURE AND TEMPERATURE.............................
5-9 SEABROOK - UNIT 1 xii Amendment No. 6
L%El BASES SECTION PAGE TABLE B 3/4.4-1 P.EACTOR VESSEL TOUGHNESS B 3/4 4-11 3/4.4.10 STRUCTURAL INTEGRITY....
B 3/4 4-16 3/4.4.11 REACTOR COOLANT SYSTEM VENTS B 3/4 4-16 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS B 3/4 5-1 3/4.5.2.
and 3/4.5.3 ECCS SUBSYSTEMS.
B 3/4 5-1 3/4.5.4 REFUELING WATER STORAGE TANK B 3/4 5-2 1/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT..............
B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS B 3/4 6-3 3/4.6.3 CONTAINMENT ISOLATION VALVES B 3/4 6-3
'3/4.6.4 COMBUSTIBLE GAS CONTROL........
B 3/4 6-3 3/4.6.5 CONTAINMENT ENCLOSURE BUILDING B 3/4 6-4 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE..................
B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.
B 3/4 7-3 3/4.7.3 PRIMARY COMPONENT COOLING WATER SYSTEM B 3/4 7-3 3/4.7.4 SERVICE WATER SYSTEM B 3/4 7-3 3/4.7.5 ULTIMATE HEAT SINK B 3/4 7-3 3/4.7.6 CONTROL ROOM SUBSYSTEMS B 3/4 7-4 3/4.7.7 SNUBBERS B 3/4 7-4 3/4.7.8 SEALED SOURCE CONTAMINATION.......
B 3/4 7-5 3/4.7.9 (THIS SPECIFICATION NUMBER IS NOT USED),
B 3/4 7-5 3/4.7.10 (THIS SPECIFICATION NUMBER IS NOT USED)
B 3/4 7-5 l
3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1. 3/4.8.2. and 3/4.8.3 A.C. SOURCES. D.C. SOURCES and DNSITE POWER DISTRIBUTION....
B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES.....
B 3/4 8-3
)
3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION B 3/4 9-1 3/4.9.2.
INSTRUMENTATION...
B 3/4 9-1 3/4.9.3 DECAY TIME B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING-PENETRATIONS....
B 3/4 9-1
.3:4.9.5 COMMUNICATIONS R 3/4 9 ~
3/4.9.6 REFUELING MACHINE.............
B 3/4 9-1 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING B 3/4 9-2 SEABROOK - UNIT 1 xi Amendment E 63
TABLE 3.7-3 (THIS TABLE NUMBER IS NOT USED) t
)
i i
)
SEABROOK-.- UNIT 1 3/4 7-24 Amendment No, M,M,63
PLANT SYSTEMS 3/4.7 10 (THIS SPECIFICATION NUMBER IS NOT USED)-
S i
i
\\
SEABROOK - UNIT 1.
3/4 7-23 Amendment No. 63
s
'PL4NTSYSTEMS W
.t BASES-3/4.7.7' ' SNUBBERS (Centinued).
' Surveillance to demonstrate 0PERABILITY is by performance of the require-
. ments of an approved inservice inspection program.
Permanent or other exemptions from the surveillance 3rogram for individual
-snubbers may be granted by the Commission. if a justifiaale basis for exemption 1s presented and.. if applicable, snubber life destructive testing was performed l
to qualify the snubbers for the applicable design conditions at either the com-pletion of their-fabrication or at a subsequent date.
Snubbers so exempted j
shall be listed in the. list of individual-snubbers indicating the extent of the exemptions.
The. service life of a snubber is established via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installe'i snubbers, seal replaced. spring replaced,.in high radiation area, in high temp rature area.
etc. ) '. The requirement.to monitor the snubber service life is included to ensure that'the snubbers' periodically undergo a performance evaluation in view of their. age'and operating conditions. These records will provide statistical bases for future consideration of snubber service life.
3/4:7.8 SEALED SOURCE CONTAMINATION
.The limitations on removable contamination for sources requiring leak
-testing, including alpha emitters, is based on 10 CFR 70.39(a)(3) limits for plutonium. This limitation will ensure that leakage from Byproduct. Source.
j and.Special Nuclear Material sources will not exceed allowable intake values, j
Sealed sources are classified into three groups according to their use, with Surveillance Requirements commensurate with the probability of damage to a i
source in that group.
Those sources which are frequently handir.d are required to be tested more often than those which are not.
Sealed sources which are continuously enclosed within a shielded mechanism (i.e... sealed sources within radiation monitoring or boron measuring devices) are considered to be. stored
-and need not be tested unless they are removed from the shielded mechanism.
3/4.7.9.(THIS SPECIFICATION NUMBER IS NOT USED.)
3/4.7.10 (THIS SPECIFICATION NUMBER-IS NOT USED.)
'SEABROOK - UNIT 1-B 3/4 7-5 Amendment.No. M, M,63