ML20135F926
| ML20135F926 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 03/12/1997 |
| From: | Milano P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20135F929 | List: |
| References | |
| NUDOCS 9703170187 | |
| Download: ML20135F926 (28) | |
Text
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UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3D66H001 NORTH ATLANTIC ENERGY SERVICE CORPORATION. ET AL*
DOCKET NO. 50-443 SEABROOK STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 50 License No. NPF-86 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by North Atlantic Energy Service Cor) oration, et al. (the licensee), dated October 17, 1996, complies wit 1 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 o>erate in conformity with the application, the provisions of t1e Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in 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 Company (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 and Power Department, Massachusetts Municipal Wholesale Electric Company, Montaup Electric Company, New England Power Company, New Hampshire Electric Cooperative, Inc., Taunton Munic pal Light Plant, and The United Illuminating Company, and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility.
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9703170187 970312 PDR ADOCK 05000443 P
. _.. _ - _ _ _. ~.. _ _ _ _ _ _ _ _ _ _ _.
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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)llows:of Facility Operating License No. NPF-86 is hereby amended to read as fo (2)
Technical Specifications The Technical' Specifications contained in Appendix A, as
[
revised through Amendment No. 50, and the Environmental Protection Plan contained in Appendix B are incorporated 1
into Facility License No. NPF-86. NAESCO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
In addition, the license is amended by redesignating existing paragraph 2.(J) as paragraph 3. and adding new paragraph 2.(J) to read as follows:
Additional Conditions j
(J).
The Additional Conditions contained in Appendix C as revised through Amendment No. 50, are hereby incorporated into this d
license. NAESCO shall operate the facility in accordance a
with the Additional Conditions.
\\
3.
This license is effective as of the date of issuance and shall i
i expire at midnight on October 17, 2026.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days of issuance.
Implementation of this i
amendment shall include the relocation of certain technical specification requirements to the appropriate licensee-controlled documents as described in the Licensee s application dated October 17, 1996, and evaluated in the staff's Safety Evaluation attached to this j
amendment.
,FOR T E NUCLEAR REGULATORY COMMISSION
)C
/
/ f. d ash ~
i Patrick A. Milano, Acting Director i
Project Directorate I-3 4
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation l
4
Attachment:
1.
Page 6 of the license and page 1 of Appendix C to the license a
2.
Changes to the Technical Specifications l
Date of Issuance: March 12, 1997 i
8
,n.
l J.
Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No. 50, are hereby incorporated into this license. NAESCO shall operate the facility in accordance with the Additional Conditions.
3.
This license is effective as of the date of issuance and shall expire at midnight on October 17, 2026.
FOR THE NUCLEAR REGULATORY COMMISSION 4
(Original signed by:
Thomas E. Murley)
Thomas E. Murley, Director Office of Nuclear Reactor Regulation Attachments / Appendices:
i 1.
Appendix A - Technical Specifications (NUREG-1386)
- 2.
Appendix B - Environmental Protection Plan 3.
Appendix C - Additional Conditions l
Date of Issuance: March 15, 1990 Revised: March 12, 1997 e
i l
4 a
i APPENDIX C 8DDITIONAL CONDITIONS j
QElj,eTING LICENSE NO. NPF-86 North Atlantic Energy Service Company (NAESCO) shall comply with the following conditions on the schedules noted below:
a s
Amendment Additional Condition Implementation Number Date 50 NAESCO is authorized to relocate certain The amendment technical spec'ification requirements to shall be licensee-controlled documents.
Implementation implemented i
of this amendment shall include the relocation within 60 days i
of these technical specification requirements from March 12, to the appropriate documents, as described in 1997.
the licensee's application dated October 17, 1996, and evaluated in the staff's Safety l
Evaluation attached to this amendment.
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1 1
Amendment No. 50 j
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ATTACHMENT TO LICENSE AMENDMENT NO. 50 i
FACILITY OPERATING LICENSE NO. NPF-86 DOCKET NO. 50-443 1
Replace the following pages of Appendix A, Technical Specifications, with the attached pages as indicated. The revised pages are identified by amendment j
number and contain vertical lines indicating the areas of change. Overleaf pages have been provided.
Remove Insert 111*
iii*
iv iv v
v vi*
vi*
i x*
ix*
X X
Xiii Xiii xiv*
xiv*
3/4 3-39*
3/4 3-39*
4 3/4 3-40 3/4 3-40 3/4 3-41 3/4 3-41 3/4 3-42 3/4 3-42 l
3/4 3-43 3/4 3-43 3/4 3-44 3/4 3-44 3/4 3-45 3/4 3-45 3/4 3-46*
3/3 3-46*
3/4 3-67 3/4 3-67 B 3/4 3-3*
- B 3/4 3-3*
B 3/4 3-4 B 3/4 3-4 B 3/4 3-5*
C 3/4 3-5*
B 3/4 3-6 B 3/4 3-6 5-9 5-9 5-10*
5-10*
i
~__._- -,-
l BDil LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS i
i SECTION PAGE 3/4.1.2 BORATIdNSYSTEMS Flow' Paths - Shutdown 3/4 1-7 Flow Paths - Operating.................
3/4 1-8 Charging Pump - Shutdown................
3/4 1-9 Charging Pumps - Operating...............
3/4 1-10 Borated' Water Sources - Shutdown............
3/4 1-11 i
Borated Water Sources - Operating 3/4 1-12 Isolation of Unborated Water Sources - Shutdown 3/4 1-14
\\
3/4.1.3 MOVABLE CONTROL ASSEMBLIES Group Height......................
3/4 1-15 TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE i
EVENT OF AN INOPERABLE FULL-LENGTH R00.........
3/4 1-17 i
Position Indication Systems - Operating 3/4 1-18 Position Indication System - Shutdown 3/4 1-19 i
Rod Drop Time 3/4 1-20 Shutdown Rod Insertion Limit..............
3/4 1-21 Control Rod Insertion Limits..............
3/4 1-22 i
i 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE 3/4 2-1 1
HEAT FLUX HOT CHANNEL FACTOR - F 3/4.2.2 NUCLEAR ENTHALPY RISE HOT CHANNEL (Z)..........
3/4 2-4
{
3/4.2.3 FACTOR........
3/42-8 3/4.2.4 QUADRANT POWER TILT RATIO 3/4 2-9 j
3/4.2.5 DNB PARAMETERS.....................
3/4 2-10 i
)
4 3/4.3 INSTRUMENTATION j
3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION 3/4 3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION 3/4 3-2 l
1 1
SEABROOK - UNIT 1 iii Amendment No. 9 j
i
)
JUDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTSS SECTION fAGE TABLE 3.3-2 (This table number is not used)
TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS......................
3/4 3-9 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 3/4 3-14 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 3/4 3-16 TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS.............
3/4 3-24 TABLE 3.3-5 (This table number is not used)
TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-31 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring For Plant Operations 3/4 3-36 TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS..................
3/4 3-37 TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS..........
3/43-39 (THIS SPECIFICATION NUMBER IS NOT USED) 3/4 3-40 (THIS SPECIFICATION NUMBER IS NOT USED) 3/4 3-41 TABLE 3.3-7 (THIS TABLE NUMBER IS NOT USED)...........
3/4 3-42 TABLE 4.3-4 (THIS TABLE NUMBER IS NOT USED)...........
3/4 3-43 (THIS SPECIFICATION NUMBER IS NOT USED) 3/4 3-44 TABLE 3.3-8 (THIS TABLE NUMBER IS NOT USED).....
3/4 3-45 Remote Shutdown System.................
3/4 3-46 TABLE 3.3-9 REMOTE SHUTDOWN SYSTEM...............
3/4 3-47 Accident Monitoring Instrumentation 3/4 3-49 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION........
3/4 3-50 TABLE 3.3-11 (This table number is not used)..........
3/4 3-53 Radioactive Liquid Effluent Monitoring Instrumentation.
3/4 3-55 TABLE 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3/4 3-56 SEABROOK - UNIT 1 iv Amendment No. 50
HD.EX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION Egg TABLE 4.3-5 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-58 Radioactive Gaseous Effluent Monitoring Instrumentation 3/4 3-60 TABLE 3.3-13 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION 3/4 3-61 TABLE 4.3-6 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-64 3/4.3.4 (THIS SPECIFICATION NUMBER IS NOT USED) 3/4 3-67 l
3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation 3/4 4-1 Hot Standby 3/4 4-2 Hot Shutdown......................
3/4 4-4 Cold Shutdown - Loops Filled..............
3/4 4-6 Cold Shutdown - Loops Not Filled............
3/4 4-7 3/4.4.2 SAFETY VALVES Shutdown........................
3/4 4-8 Operating 3/4 4-9 3/4.4.3 PRESSURIZER 3/4 4-10 3/4.4.4 RELIEF VALVES 3/4 4-11 3/4.4.5 STEAM GENERATORS....................
3/4 4-13 TABLE 4.4-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION 3/4 4-18 TABLE 4.4-2 STEAM GENERATOR TUBE INSPECTION 3/4 4-19 3/4.4.6 REACTOR COOLANT SYSTEM LEAXAGE Leakage Detection Systems 3/4 4-20 Operational Leakage 3/4 4-21 TABLE 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES..
3/4 4-24 3/4.4.7 CHEMISTRY 3/4 4-25 TABLE 3.4-2 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS.......
3/4 4 3/4.4.8 SPECIFIC ACTIVITY 3/4 4-27 SEABROOK - UNIT 1 v
Amendment No. 50
MK l
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS' SECTION M
FIGURE 3.4-1 DOSE EQUIVALENT I-131 REACTOR COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWER t
WITH THE REACTOR COOLANT SPECIFIC ACTIVITY > IpCi/ gram DOSE EQUIVALENT I-131 3/4 4-28 TABLE 4.4-3 REACTOR COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM 3/4 4-29 3/4.4.9 PRESSURE / TEMPERATURE LIMITS i
General 3/4 4-30 FIGURE 3.4-2 REACTOR C0CLANT SYSTEM HEATUP LIMITATIONS -
APPLICABLE UP TO 16 EFPY................
3/4 4-31 FIGURE 3.4-3 REACTOR COOLANT SYSTEM C00LDOWN LIMITATIONS -
APPLICABLE UP TO 16 EFPY................
3/4 4-32 Pressurizer 3/4 4-33' Overpressure Protection Systems 3/4 4-34 FIGURE 3.4-4 RCS COLD OVERPRESSURE PROTECTION SETPOINTS 3/4 4-36 3/4.4.10 STRUCTURAL INTEGRITY..................
3/4 4-37 3/4.4.11 REACTOR COOLANT SYSTEM VENTS..............
3/4 4-38 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS Hot Standby, Startup, and Power Operation 3/4 5-1 Shutdown........................
3/4 5-3 3/4.5.2 ECCS SUBSYSTEMS - T, GREATER THAN OR EQUAL TO 350*F 3/4 5-4 3/4.5.3 ECCS SUBSYSTEMS - T LESS THAN 350*F 3/4 5-8 ECCS Subsystems - T,, Equal _To or Less Than 200*F 3/4 5-10 3/4.5.4 REFUELING WATER STORAGE TANK..............
3/4 5-11 3/4.6 CONTAIMENT SYSTEMS 3/4.6.1 PRIMARY CONTAIMENT Containment Integrity 3/4.6-1 Containment' Leakage 3/4 6-2 SEABROOK - UNIT 1 vi
lilD.G LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS i
l SECTION Egig j
3/4.9.4 CONTAIMENT BUILDING PENETRATIONS 3/4 9-4' 3/4.9.5 ComuN I C AT I ON S.....................
3/4 9-S 3/4.9.6 REFUELING MACHINE 3/4 9-6 i
3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE AREAS 3/4 9-7 l
3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION i
High Water Level....................
3/4 9-8 i
Low Water Level 3/4 9-9 l
3/4.9.9 CONTA1 MENT PURGE AND EXHAUST ISOLATION SYSTEM.....
3/4 9-10 3/4.9.10 WATER LEVEL - REACTOR VESSEL..............
3/4 9-11 3/4.9.11 WATER LEVEL - STORAGE POOL...............
3/4 9-12 3/4.9.12 FUEL STORAGE BUILDING EMERGENCY AIR CLEANING SYSTEM 3/4 9-13 j
3/4.9.13 SPENT FUEL ASSEMBLY STORAGE 3/4 9-16 4
FIGURE 3.9-1 FUEL ASSEMBLY BURNUP VS. INITIAL ENRICHMENT FOR SPENT FUEL ASSEMBLY STORAGE..........
3/4 9-17 3/4.9.14 NEW FUEL ASSEMBLY STORAGE 3/4 9-18 j
i 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN 3/4 10-1 j
3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS.
3/4 10-2 3/4.10.3 PHYSICS TESTS 3/4 10-3 3/4.10.4 REACTOR COOLANT LOOPS 3/4 10-4 i
3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN 3/4 10-5 i
I 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS i
Concentration 3/4 11-1 Dose..........................
3/4 11-2 I
Liquid Radwaste Treatment System............
3/4 11-3 l
l Liquid Holdup Tanks 3/4 11-4 l
3/4.11.2 GASEOUS EFFLUENTS l
Dose Rate 3/4 11-5 i
Dose - Noble Gases...................
3/4 11-6 Dose - Iodine-131, Iodine-133, Tritium, and Radioactive i
Material in Particulate Form..............
3/4 11-7 j
Gaseous Radwaste Treatment System 3/4 11-8 i
Explosive Gas Mixture - System.............
3/4 11-9 1
3/4.11.3 SOLID RADI0 ACTIVE WASTES................
3/4 11-10 3/4.11.4 TOTAL DOSE.......................
3/4 11-12 l
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING j
3/4.12.1 MONITORING PROGRAM...................
3/4 12-1 i
j SEABROOK - UNIT 1 ix Amendment No. 34
~. -
_g.__.
i MX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION E
3/4.12.2 LAND USE CENSUS 3/4 12-3 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM...........
3/4 12-5 3.0/4.0 BASES 3/4.0 APPLICABILITY B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATICN CONTROL....................
.B 3/4 1-1 3/4.1.2 BORATION SYSTEMS....................
B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES...............
B 3/4 1-3 3/4.2 POWER DISTRIBUTION LIMITS B 3/4 2-1 3/4.2.1 AXIAL FLUX DIFFERENCE B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR B 3/4 2-2 3/4.2.4 QUADRANT POWER TILT RATIO B 3/4 2-3 3/4.2.5 DNB PARAMETERS.....................
B 3/4 2-4 3/4.3 INSTRUMENTATION j
3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.......
B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION...............
B 3/4 3-3 3/4.3.4 (THIS SPECIFICATION NUMBER IS NOT USED)
B 3/4 3-6 l
3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION B 3/4 4-1 3/4.4.2 SAFETY VALVES B 3/4 4-1 3/4.4.3 PRESSURIZER B 3/4 4-2 3/4.4.4 RELIEF VALVES B 3/4 4-2 3/4.4.5-STEAM GENERATORS....................
B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE.............
B 3/4 4-3 3/4.4.7 CHEMISTRY B 3/4 4-5 3/4.4.8 SPECIFIC ACTIVITY B 3/4 4-5 3/4.4.9 PRESSURE / TEMPERATURE LIMITS B 3/4 4-7 FIGURE B 3/4.4-1 FAST NEUTRON FLUENCE (E>1MeV) AS A FUNCTION OF
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FULL POWER SERVICE LIFE................
B 3/4 4-9 FIGURE B 3/4.4-2 (This figure number not used).........
B3/4 4-10 SEABROOK - UNIT 1 x
Amendment No. 50
ED.El i
5.0 DESIGN FEATURES 4
l SECTION PAGE i
5.3 REACTOR CORE 5.3.1 FUEL ASSEMBLIES 5-9 i
5.3.2 CONTROL R00 ASSEMBLIES.................
5-9 5.4 REACTOR COOLANT SYSTEM i
5.4.1 DESIGN PRESSURE AND TEMPERATURE 5-9 5.4.2 VOLUME.........................
5-9 5.5 (THIS SPECIFICATION NUMBER IS NOT USED) 5-9 l
5.6 FUEL STORAGE i
l 5.6.1 CRITICALITY 5-10 5.6.2 ORAINAGE........................
5-10 l
5.6.3 CAPACITY........................
5-10 l
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5-10 TABLE 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS........
5-11 6.0 ADMINISTRATIVE CONTROLS i
j 6.1 RESPONSIBILITY.......................
6-1
}
6.2 ORGANIZATION........................
6-1 i
6.2.1 0FFSITE AND ONSITE ORGANIZATIONS............
6-1 6.2.2 STATION STAFF 6-2 FIGURE 6.2-1 (This figure number is not used) 6-3 FIGURE 6.2-2 (This figure number is not used) 6-3 4
TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION...........
6-4 l
6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)
Function........................
6-5 Composition 6-5 Responsibilities....................
6-5 l
Records 6-5 6.2.4 SHIFT TECHNICAL ADVISOR 6-5 l
6.3 ~ TRAINING 6-5 1
SEA 8 ROOK - UNIT 1 xiii Amendment No. 50 i
DDIX 6.0 ADMINISTRATIVE CONTROLS SECTION EME 6.4 REVIEW AND AUDIT 6-6 6.4.1 STATION OPERATION REVIEW C0fti!TTEE (SORC)
Function........................
6-6 Composition 6-6 Alternates.......................
6-6 Meeting Frequency 6-6 Quorum.........................
6-6 Responsibilities....................
6-7 Records 6-8 6.4.2 STATION QUALIFIED REVIEWER PROGRAM...........
6-8 1
Function........................
6-8 1
Responsibilities....................
6-8 Records 6-8A Training and Qualification...............
6-8A 6.4.3 NUCLEAR SAFETY AUDIT REVIEW C0ffilTTEE (NSARC)
Function........................
6-8B Composition 6-8B Alternater.......................
6-8B Consultants 6-8B Meeting Frequency 6-8B Quorum.........................
6-8B Review.........................
6-9 l
Audits.........................
6-10 Records 6-11 6.5 REPORTABLE EVENT ACTION 6-11 6.6 SAFETY LIMIT VIOLATION...................
6-11 6.7 PROCEDURES AND PROGRAMS 6-12 6.8 REPORTING REQUIREMENTS 1
6.8.1 ROUTINE REPORTS 6-14A Startup Report.....................
6-14A Annual Reports.....................
6-15 Annual Radiological Environmental Operating Report...
6-15 Annual Radioactive Effluent Release Report.......
6-17 Monthly Operating Reports 6-18 1
CORE OPERATING LINITS REPORT..............
6-18
)
6.8.2 SPECIAL REPORTS 6-19 i
SEA 8R00K - UNIT 1 xiv Amendment No. 34
r M
TABLE 4.3-3 l
-t E
RADIATII)t MONITORIIG
- 'IS"tUME(TAT:0N 20R PLANT I
l OP E tATIONS SULVE.
. LULGCE tEOU: : REM ENTS DIGITAL g
CHANNEL MODES FOR WHICH CHANNEL CHANNEL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REOUIRED
~
- 1. Containment
{
- a. Containment - Post LOCA -
f Area Monitor S
R Q
All
- b. RCS Leakage Detection i
- 1) Particulate Radio-S R
Q 1, 2, 3, 4 activity
- 2) Gaseous Radioactivity S
R Q
1, 2, 3, 4 i
t
- 2. Containment Ventilation Isolation l
M
- a. On Line Purge Monitor S
R Q
l 2 6I, 3, 4 l
- b. Mani ulator Crane Area S
R Q
i Moni or 4
j
- 3. Main Steam Line S
R Q
1,2,3,4
- 4. Fuel Storage Pool Areas
- a. Radioactivity-High-Gaseous Radioactivity S
R Q
t
- 5. Control Room Isolation
- a. Air Intake Radiation Level i
1 East Air Intake S
R Q
All 2)WestAirIntake g
)
S R
Q All l
E-
- 6. Primary Component Cooling Water
[
5
- a. Loop A S
R Q
All A
- b. Loop B S
R Q
All
=
TABLE NOTATIONS
- With irradiated fuel in the fuel storage pool areas.
l w
i
- During CORE ALTERNATIONS or movement of irradiated fuel within the containment.
o t
)
i
_.... = _ _ _ _ _. _ _... _... _. _ _ _ _ _ _ _ _ _. _ _ _ _. _ _. _ _. _ _ _ _ _ _ _.. _. _ _ _ _. _.. _ _ _. _. _.... _
INSTRUMENTATION 3.3.3.2 (THIS SPECIFICATION NUMBER IS NOT USED)
J SEABROOK - UNIT 1 3/4 3-40 Amendment No. 50
..-_..~ _.._..._ _._ _ _--___._-._. _ ___.._.. -_-._ _.._.._
e i
INSTRUMENTATION l
3.3.3.3 (THIS SPECIFICATION NUMBER IS NOT USED j
4 4
1 4
1 i
i i
i d
I 4
4 s
l 4
+
i l
4 i
i i
l l
SEABROOK - UNIT 1 3/4 3-41 Amendment No. 50 4
1-w,
_ _ _ _ _ _. =
TABLE 3.3-7 (THIS TABLE NUMBER IS.NOT USED) i-SEABROOK - UNIT 1 3/4 3-42 Amendment No. 50
TABLE 4.3-4 (THISTABLENUMBERISNOTUSED) i l
J SEABROOK - UNIT 1 3/4 3-43 Amendment No. 50
INSTRUMENTATION 3.3.3.4 fTHIS SPECIFICATION NUMBER IS NOT USED) i l
i l
e SEABROOK - UNIT 1 3/4 3-44 Amendment No. 50
TABLE 3.3-8 (THIS TABLE NUMBER IS NOT USED) s SEABROOK - UNIT 1 3/4 3-45 Amendment No. 50
l INSTRUMENTATION MONITORING INSTRUMENTATION
}
REMOTE 5HUTDOWN SYSTEM i
i LIMITING CONDITION FOR OPERATION i
3.3.3.5 The Remote Shutdown System transfer switches, power, controls and j
monitoring instrumentation channels sSown in Table 3.3-9 shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3.
i ACTION:
i l
a.
With the number of OPERABLE remote shutdown monitoring channels less than the Ninimum Channels OPERABLE as required by Table 3.3-9, l
restore the inoperable channel (s) to OPERABLE status within 7 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The provisions of j
Specification 3.0.4 are not applicable.
{
j b.
With the number of OPERABLE remote shutdown monitoring channels
)
less than the Total Number of Channels as required by Table 3.3-9, within 60 days restore the inoperable channel (s) to OPERABLE status or, pursuant to Specification 6.8.2, submit a Special Report that defines the corrective action to be taken.
c.
With one or more Remote Shutdown System transfer switches, power, or control circuits inoperable, restore the inoperable switch (s)/
l circuit (s) to OPERABLE status within 7 days, or be in HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The provisions of Specification 3.0.4 are not applicable.
l SURVEILLANCE REQUIREMENTS 4.3.3.5.1 Each remote shutdown monitoring instrumentation channel in Table 3.3-9 shall be demonstrated OPERABLE:
a.
Every 31 days by perfomance of a CHANNEL CHECK, and b.
E'very 18 months by perfomance of a CHANNEL CALIBRATION.
4.3.3.5.2 Each Remote Shutdown System transfer switch, power and control circuit listed in Table 3.3-9, including the actuated components, shall be j
demonstrated OPERABLE at least once per 18 months.
4 SEABROOK - UNIT 1 3/4 3-46
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INSTRUMENTATION 3/4.3.4 (THIS SPECIFICATION NUMBER IS NOT USED)
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SEABROOK - UNIT 1 3/4 3-67 Amendment No. 50
INSTRUMENTATION i
i BASES 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued)
Injection pumps start and automatic valves position, (2) Reactor trip, (3) feedwater isolation, (4) startup of the emergency diesel generators, j
(5) containment spray pumps start and automatic valves position, (6) containment isolation, (7) steam line isolation, (8) turbine trip, (9) emergency feedwater pumps start and automatic valves position, (10) containment cooling fans start and automatic valves position, and (11) automatic service water valves position.
The Engineered Safety Features Actuation System interlocks perform the following functions:
l P-4 Reactor tripped - Actuates Turbine trip, closes main feedwater j
valves on T below Setpoint, prevents the opening of the main feedwaterv7aveswhichwereclosedbyaSafetyInjectionorHigh Steam Generator Water Level signal, allows Safety Injection block so that components can be reset or tripped.
Reactor not tripped - prevents manual block of Safety Injection.
P-ll On increasing pressurizer pressure, P-Il automatically reinstates Safety Injection actuation on low pressurizer pressure. On decreasing pressure, P-11 allows the manual block of Safety Injection actuation on low pressurizer pressure, and the manual block of SI and steamline isolation on steamline low pressure. On the manual block of steamline low pressure, manual block of steamline low pressure automatically initiates steamline isolation on steam generator pressure negative rate - high.
P-14 On increasing steam generator water level, P-14 automatically trips the turbine and all feedwater isolation valves; inhibits feedwater control valve modulation; and blocks the start of the startup feed-water pump.
3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING FOR PLANT OPERATIONS The OPERASILITY of the radiation monitoring instrumentation for plant operations ensures that:
(1) the associated action will be initiated when the radiation level monitored by each channel or combination thereof reaches its Setpoint, (2) the specified coincidence logic is maintained', and (3) sufficient
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redundan::y is maintained to permit a channel to be out of service for testing or maintenance. The radiation monitors for plant operations sense radiation levels in selected plant systems and locations and determine whether or not predetermined limits are being exceeded.
If they are, the signals are combined into logic matrices sensitive to combinations indicative of various accidents SEABROOK - UNIT I B 3/4 3-3
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INSTRUMENTATION BASES MONITORING 1NSTRUNENTATION 3/4.3.3.1 RADIATION MONITORING FOR PLANT OPERATIONS (Continued) and abnormal conditions. Once the required logic combination is completed, the 4
system sends actuation signals to initiate alarms or automatic isolation action and actuation of Emergency Exhaust or Ventilation Systems.
3/4.3.3.2 (THIS SPECIFICATION NUMBER IS NOT USED) 3/4.3.3.3 (THIS SPECIFICATION NUMBER IS NOT USED) 3/4.3.3.4 (THISSPECIFICATIONNUMBERISNOTUSED) 3/4.3.3.5 REMOTE SHUTDOWN SYSTEM 3
The OPERABILITY of the Remote Shutdown System ensures that sufficient capability is available to permit safe shutdown of the facility from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of l
l Appendix A to 10 CFR Part 50.
i SEABROOK - UNIT 1 8 3/4 3-4 Amendment No. 50
INSTRUMENTATION i
BASES
)
MONITORING INSTRUMENTAT' ION f
3/4.3.3.5 REMOTE SHUTDOWN SYSTEM (Continued) 1 The OPERA 81LITY of the Remote Shutdown System ensures that a fire will
)
not preclude achieving safe shutdown. The Remote Shutdown System instrumentation, control, and power circuits and transfer switches necessary to eliminate effects of the fire and allow operation of instrumentation, control 1
and power circuits required to achieve and maintain a safe shutdown condition j
are independent of areas where a fire could damage systems normally used to shut down the reactor. This capability is consistent with General Design j
Criterion 3 and Appendix R to 10 CFR Part 50.
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3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATI0fi The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and j
assess these variables following an accident. This capability is consistent i
with the recommendations of Regulatory Guide 1.97, Revision 3, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," May 1983 and NUREG-0737, " Clarification of TMI Action Plan Requirements," November 1980.
i 3/4.3.3.7 (This specification number is not used.)
3/4.3.3.8 (This specification number is not used.)
3/4.3.3.9 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.
The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
3/4.3.3.10 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.
The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alam/ trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the WASTE GAS HOLDUP SYSTEM. The OPERABILITY and use of this instrumentation is consistent with the requirenents SEABROOK - UNIT I B 3/4 3-5
INSTRUNENTATION BASES MDNITORING INSTRUMENTATION 3/4.3.3.10 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (Continued) of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. The sensitivity of any noble gas activity monitors used to show compliance with the gaseous effluent release requirements,of Specification 3.11.2.2 shall be such that concentrations as low as 1 X 10' gi/cc are measurable.
3/4.3.4 (THIS SPECIFICATION NUMBER IS NOT USED) l SEABROOK - UNIT I B 3/4 3-6 Amendment No. 50
DESIGN FEATURES i
DESIGN PRESSURE AND TEMPERATURE i
5.2.2 The containment building is designed and shall be maintained for a i
maximum internal pressure of 52.0 psig and a temperature of 296*F.
5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assemblies with each fuel assembly I
containing 264 fuel rods clad with Zircaloy-4. Each fuel rod shall have a nominal active fuel ler.gth of 144 inches. The initial core loading shall have a maximum enrichment of 3.15 weight percent U-235.
Reload fuel shall be i
similar in physical design to the initial core loading and shall have a maximum enrichment of 5.0 weight percent U-235.
CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 57 full-length control rod assemblies. The full-length control rod assemblies shall contain a nominal 142 inches of absorber material.
The nominal values of absorber material shall be 80% silver,15%
indium, and 5% cadmium. All control rods shall be clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:
a.
In accordance with the Code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and c.
For a temperature of 650*F, except for the pressurizer which is 680*F.
VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 12,255 cubic feet at a nominal T of 588.5'F.
m 5.5 (THIS SPECIFICATION NUMBER IS NOT USED) l i
l SEABROOK - UNIT 1 5-9 Amendment No. 50
DESIGN FEATURES l
5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:
A k,,ted water, which includes margin for uncertainty inequivalen a.
unbora calculation methods and mechanical tolerances with a 95%
probability at a 95% confidence level.
b.
A nominal 10.35 inch center-to-center distance between fuel assemblies placed in the storage racks.
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5.6.1.2 The new fuel storage racks are designed and shall be maintained with:
A k,,,ted water, which includes margin for uncertainty in equivalent to less than or equal to 0.95 when flooded with a.
unbora calculational methods and mechanical tolerances with a 95%
i probability at a 95% confidence level.
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b.
Ak equivalent to less than or equal to 0.98 when aqueous foam i'
modNationisassumed,whichincludesmarginforuncertaintyin calculational methods and mechanical tolerances with a 95%
probability at a 95% confidence level.
j c.
A nominal 21 inch center-to-center distance between fuel assemblies j
placed in the storage racks.
DRAINAGE 4
i 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 14 feet 6 inches.
CAPACITY
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~ 5.6.3 ~ The spent fuel storage po'o1 is'designe'd and shal1 be maintained with a
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storage capacity limited to no more than 1236 fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 4
5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1, 1
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SEABROOK - UNIT 1 5-10 Amendment No. 6
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