ML20082M894
| ML20082M894 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 08/27/1991 |
| From: | Shankman S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20082M898 | List: |
| References | |
| NUDOCS 9109060084 | |
| Download: ML20082M894 (11) | |
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UNITED STATES i
NUCLEAR REGULATORY COMMISSION 6
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WASHINGTON, D C. 20606 o
s ~...+ f PUBLIC SERVICE COMPANY OF NEW HAMPSHIRE ET AL.*
u D_0C,KET 140. 50-443 SEABROOK STATION, UNIT NO. I hE5FPEEN. J 0, f f,CJ L,l J Y,0P E,R,AT I N G L I CE N S E Amendment flo. 6 License No. NPF-86 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Company of tiew Hampshire (the licensee), acting for itself and as agent and representative of the 11 other utilities listed below and hereafter referred to as licensees, dated March 18, 1991 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 f acility will operate in conformity with the application, the provisions of the 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 Connission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this ariendnent 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 aniendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- Public Service Company of flew Hanpshire is authorized to act as agent for the:
Canal Electric Company, The Connecticut Light and Power Company, EUA Power Corporation, Hudson Light & Power Eerartoent, Massachusetts tiunicipal Wholesale Electric Conpany, Montaup Electric Corpany, tiew England Power Company, New Hampshire Electric Cooperative, Inc., Teunton tiunicipal Light Plant, The United Illuminating Cortpany, and Vencrt Electric Generation and Transmission Cooperative, Inc., and has exclusise responsibility and control over the physical construction, operation ar.d r eintenance of the f acility.
9109060084 910827 PDR ADDCK 05000443 p
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license i
amendment, and paragraph 2.C.(2) of Facility Operating License No NPF-86 is hereby amended to read as follows:
)
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 6
, and the Environmental Protection Plan contained in Appendix B are incorporated into facility License No.
PSNH 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 and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION ut Nh L
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' usan Frant-Shankman, Acting Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 27. 1991 4
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i ATTACHMENT TO LICENSE-AMENDMENT NO. 6 l
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FACILITY OPERATING LICENSE NO.'NPF-B6 DOCKET NO. 50-443 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and r
contain vertical lines indicating the area of change.
r i
Remove Insert j
ix ix xii xii 3/4 9-16 i
3/4 9-17 j
3/4 9-18 l
B 3/4 9-3 B 3/4 9-3 i
5-9 5-9
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5-10 5-10 i
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INDEX i
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANC _E REQUIREMENTS SECTION PAGE 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.....................
3/4 9-4 3/4.9.5 COMMUNICATIONS............................s 3/4 9-5 3/4.9.6 REFUELING MACHINE...................
.......s...
3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE AREAS..................
3/4 9-7 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Level.........................................
3/4 9-8 Low Water Lave1..........................................
3/4 9-9 3/4,9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM...........
3/4 9-10 l
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 3/4.9.13 SPENT FUEL ASSEMBLY ST0 RAGE.............................,
3/4 9-16 FIGURE 3.9-1 FUEL ASSEMBLY BURNUP VS, 1NITIAL ENRICHMENT........
FOR SPENT FUEL ASSEMBLY ST0 RAGE.....................
3/4 9-17 3/4.9.14 NEW FUEL ASSEMBLY ST0 RAGE.......................<........
3/4 9-18 j
3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN..........................................
3/4 10-1 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 L00PS...................................
3/4 10-4 3/4.10.5 POSITION INDICATION SYSTEM - SHUTD0WN....................
3/4 10-5 3/4.10.6 REACTOR COOLANT LOOPS........
3/4 10-6 1
3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration.........................................
3/4 11-1 Dnse.............
3/4 11-2
,t Liquid Radwaste Treatment Systt:
3/4 11-3 Liquid Heldup Tanks..........
3/4 11-4 i
3/4.11.2 GASEGUS EFFLUENTS Dose Rate.......
3/4 11-5 Dose - Noble Gases...................................
3/4 11-6 Dose - Iodine 131, Iodine-133, Tritium, and Radioactive i
Material in Particulate Form...
3/4 11-7 Gaseous Radwaste Treatment System.....................
3/4 11-8 Explosive Gas Mixture - System.
3/4 11-9 3/4.11.3 SOLID RADI0 ACTIVE WASTES...........................
3/4 11-10 3/4.11.4 TOTAL 00SE............
3/4 11-12 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING I
3/4.12.1 MONITORING PROGRAM.
3/4 12-1 i
SEABROOK - UNIT 1 ix Amendment No. 6 l
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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 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN...........................................
B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS....
B 3/4 10-1 3/4.10.3 PHYSICS TESTS.............................................
B 3/4 10-1 3/4.10.4 REACTOR COOLANT L00PS.....................................
B 3/4 10-1 3/4.10.5 POSITION INDICATION SYSTEM - SHUTD0WN.....................
B 3/4 10-1 3/4.10.6 REACTOR COOLANT LOOPS...................................
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 GASE0US EFFLUENTS....................
B 3/4 11-2 3/4.11.3 SOLID RADI0 ACTIVE WASTES.........................
B 3/4 11-5 3/4.11.4 TOTAL 00SE...............................................
B 3/4 11-5 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM.........
B 3/4 12-1 3/4.12.2 LAND USE CENSUS..........................................
B 3/4 12-1 3/4.12.3 INTERLABORATORY COMPARISUN PROGRAM...........
B 3/4 12-2 5.0 DESIGN FEATURES 5.1 SITE 5.1.1 EXCLUSION AREA..............
5-1 5.1. 2 LOW POPULATION ZONE.........
5-1 5.1. 3 MAPS DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADI0 ACTIVE GASE0US AND LIQUID EFFLUENTS..
5-1 FIGURE 5.1-1 SITE AND EXCLUSION AREA BOUNDARY...................
5-3 FIGURE 5.1-2 LOW POPULATION ZONE.,
5-5 FIGURE 5.1-3 LIQUID EFFLUENT DISCHARGE LOCATION.
5-7 5.2 CONTAIN'!ENT 5-1 5.2.1 CONFIGURATION.
5.2.2 DESIGN PRESSURE AND TEMPERATURE..
5-9 l-SEABROOK - UNIT 1 xii Amendment No. 6 i
REFUELING OPERATIONS 3/4.9.13 SPENT FUEL ASSEMBLY STORAGE LIMITING CONDITION FOR OPFRATION 3.9.13 Fuel assemblies stored in the Spent Fuel Pool shall be placed in.the spent fuel storage racks according to the criteria shown in Figure 3.9-1.
APPLICABILITY:
Whenever fuel is in the Spent Fuel Pool.
ACTION:
a.
With the requirements of the above specification not satisfied, suspend all other fuel movement within the Spent Fuel Pool and move the non-complying fuel assemblies to allowable locations in the Spent Fuel Pool in accordance with figure 3.9-1, b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.13.1 The burnup of each fuel assembly to be stored in the Spent Fuel Pool shall be determined from it's measured burnup r.istory prior to storage in the Spent Fuel Pool.
A complete record of each assembly shall be maintained as long as that fuel assembly is retained on-site, 4.9.13.2 After fuel assembly (ies) movement into or within the Spent Fuel Pool, the position of the fuel assembly (ies) that was (were) moved shall be checked and independently verified to be in accordance with the criteria in Figure 3.9-1 SEABROOK - UNIT 1 3/c 9-H Amendment No. 6
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Figure 3.9-1 Fuel Assembly Eurnup 'is. Initial Enrichment For Spent Fuel Asterily Storage
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.Arendment No. 6 un s,w_
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REFUELING OPERATIONS 3/4.9.14 NEW FUEL ASSEMBLY STORAGE LIMITING CONDITION FOR OPERATION 3.9.14 The New Fuel Storage Vault may be maintained with a full loading of 90 assemblies with fuel enrichment up to 3.675 w/o 2asV.
The loading must be reduced to 81 assemblies for enrichments from 3.675 to 5.0 w/o 23su by limiting the fuel assembly placement in the central column of the New Fuel Storage Vault to every other location.
APPLICABILITY:
Whenever fuel is in the New Fuel Storage Vault.
ACTION:
a.
With the requirements of the above specifications not satisfied, suspend all other fuel movement within the New Fuel Storage Vault and move the non-complying fuel assemblies to allowable locations in the New Fuel Storage Vault in accordance with the requirements of the above specification, b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.14.1 After fuel assembly (ies) movement into or within the New Fuel Storage Vault, the position of the new fuel assembly (ies) that was (were) moved shall be checked and independently verified to be in accordance with the requirements of the above specification.
I SEABROON - UNIT 1 3/4 9-lE Amendment No. 6 I
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t REFUELING OPERATIONS BASES 3/4.9.12 FUEL STORAGE BUILDING EMERGENCY AIR CLEANING SYSTEM (Continued)
I for at least 10 continuous hours in a 31-day period is sufficient to reduce i
the buildup of moisture on the adsorbers and HEPA filters.
The OPERABILITY of I
this system and the resulting iodine removal capacity are consistent with the assumptions of the safety analyses.
ANSI N510-1980 will be used as a proce-dural guide for surveillance testing.
3/4.9.13 SPENT FUEL ASSEMBLY STORAGE i
Restrictions on placement of fuel assemblies of certain enrichments
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within the Spent Fuel Pool is dictated by Figure 3.9-1.
These restrictions ensure that the K,ff of the Spent Fuel Pool will always remain less than 0.95 assuming the pool to be flooded with unborated water.
The restrictions delineated in Figure 3.9-1 and the action statement are consistent with the criticality safety analysis performed for the Spent Fuel Pool as documented in the FSAR.
3/4.9.14 NEW FUEL ASSEMBLY STORAGE Restrictions on placement of fuel assemblies of certain enrichments within f
the New Fuel Storage Vault is dictated by Specification 3/4.9.14. These restric-i tions ensure that the Keff of the New Fuel Storage Vault will always remain less than 0.95 assuming the area to be flooded with unborated water.
In addition, these restrictions ensure that the Kgff of the New Fuel Storage Vault will always remain less than 0.98 when aqueous foam moderation is assumed.
The restrictions delineated in Specification 3/4.9.14 and the action statement are consistent with the criticality safety analysis performed for the New fuel Storage Vault as documented in the FSAR.
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i SEABROOK - UNIT 1 B 3/4 9-3 Amendment No. 6
DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5.2.2 The containment building is designed and shall be maintained for a r aximum 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 con-taining 264 fuel rods clad with Zircaloy-4.
Each fuel rod shall have a nominal active fuel length of 144 inches.
The initial core loading shall have a maximum enrichment of 3.15 weight percent U-235.
Reload fuel shall be similar in phy-sical design to the initial core loading and shall have a maximum enrichment of 5.0 weight percent U-235.
CONTROL R0D 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% in-dium, and 5% cadmium.
All control rods shall be clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.7 The Reactor Coolant System is designed and shall be maintained:
6.
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 12,265 cubic feet at a nominal T f 588.5 F.
avg 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
SEABROOK - UNIT 1 5-9 Amendment No. 6
l DESIGN FEATURES i'
5.6 fuel STORAGE CRITICALITY
- 5. 6.1.1 The spent fuel storage racks are designed and shall be maintained with:
\\
A k,77 equivalent to less than or equal to 0.95 when flooded with a.
unborated water, which includes margin for uncertainty in calcula-tion 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.
5.6.1.2 The new fuel storage racks are designed and shall be maintained with; a.
Akeff equivalent to less than or equal to 0.95 when flooded with unborated water, which includes margin for uncertainty in calcula-tional methods and mechanical tolerances with a 95% probability at a 95% confidence level.
b.
Akeff equiva'ent to less than or equal to 0.98 when aqueous foam moderation is assumed, which includes margin for uncertainty in calculational methods and mechanical tolerances with a 95% probability at a 95% confidence level.
c.
A nominal 21 inch center-to-center distance between fuel assemblies placed in the storage racks.
DRAINAGE 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 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1236 fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 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.
SEABROOK - UNIT 1 5-Ir Amendment No. f>
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