ML20087E576
| ML20087E576 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 01/17/1992 |
| From: | Sylvia B NIAGARA MOHAWK POWER CORP. |
| To: | |
| Shared Package | |
| ML20087E574 | List: |
| References | |
| NUDOCS 9201210299 | |
| Download: ML20087E576 (8) | |
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IMITED STATES NUC, LEAR REGULAMitJ CONNISSION In the matter of-
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NiaEara Hohawk Power Corporation
) Docket No. 50-410
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(Nine Mile Point Nuclear Station Unit No. 2
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APPLICATION FOR AFENDNENT TO OPERATING LICENSE Pursuant to Section 50.90 of the Regulations of the Nuclear Regulatory Commission, Niagara Mohawk Power Corporation, holder of Pacility Operating -
License No; NPF-69, hereby requests the revision of license condition 2.C.(3)b, the deletion of Itcense condition 2.C.(3)b.i and 11, and the revision of license condition 2.C. (3)c as set forth in the license.
The proposed changes have been reviewcd in accordan:e with Section 6.5 of the Technical Specifications.
l The proposed changes to the license are set forth in Attachment A to this application.- License condition 2.C.(3) addresses Fuel Storage and Handling and the-associated limitations on fuel assembly location during fuel movement.
License condition 2.C.(3)b.i and 11 are deleted license condition 2.C.(3)b is revised to read:
"When not in the reactor vessel, no more than three fuel assemblies shall be allowed outside of their shipping containers or storage racks 'in the New Fuel Vault or Spent Fuel Storage Facility"; and license condition:2.C.(3)c is revised by changing "four" to "three" (fuel assemblies) in the first line.
The proposed changes vill not authorize any change in the type of effluents or in the authorized power level of the facility.
Supporting information and
.' analysis the.t demonstrate the proposed changes involve no significant' hazards L
consideration pursuant to 10 CFR $ 50.92~ are inched in Attachment B.
The j
-purpose =of requesting this license amendmr
.s to provide. necessary flexibility during refueling operations, achieve consistency with Nine Mile l
Point. Unit 2 Updated L Safety Analysis Report Section 9.1.4.2.11, and achieve l~
-consistency with normal Boiling Vater Reactor fuel handling practices.
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5 VHEREFORE, Applicar t respectfully requests that the Facility Operat'ng License -
No. NPF-69 be amended in the form attached hereto as Attachment A.
NIAGARA H0llAVK POVER CORPORATION By N
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.B.'R11'ph Sflvia
~7 Exec,Vice'Presiddt-Nuclear Subscribed and Sworn to before me on. this;/7 day of
&1992.
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/ NOTARY j'dBLIC
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BEVERLY w R m -
ttotary Publ< Stateof New Yoit
@el.in Oswego Ca No. 4644379 My Commission Exp.
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.. g ATTACmRNT A NIAGARA MORAVK POVER CORPORATION LICENSE NO, NPF-69 DOCKET Ho. 50-410 Proposed Cianggs to the 1.icense l
Replace existing page 4 of the license with the attached page. This page has been provided with marginal markinEs to indicate the changes.
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Technical SoecifLcations and Environmental Protection Plan The Technical Specifications contained in Appendix A and the
- Environmental Protection Plan contained in Appendix B, both of which are attached hereto,_are hereby incorporated into this license. Niagara Mohavk_ Power Corporation shall operate the facility in accordance with the_ Technical Specifications and the Environmental Protection Plan.
(3)
LLel Stongg and HaDiline (Section 9.1. SSER 4)*
a.
Fuel assemblies, when stored in their shipping containers, shall be stacked no more than three containers high.
b.
When not in the reactor vessel, no more than three fuel assemblies shall-be allowed outside of their shipping containers or storage Jacks in the New Puel Vault or Spent Fuel Storage Facility, The above three fuel assemblies shall maintain a minimum edge-to~
c.
edge spacing of' twelve (12) inches from the shipping container array and approved storage rack locations.
.d.-
The New Fuel Storage Vault shell have-no more than ten fresh fuel assemblies uncovered at any one time.
(4)
-Turbine System Maintenan3e Program _(jaction 3.5.ladWR1 Niagara-Hohawk Power Corporation shall aubmit fot NRC approval by October 31, 1989, a turbine system maintenance program based on the manufacturer's calculations of missile generation probabilities.
(5)
Inservice Inspection (Sections 5.2.4.3 and 6.6.3. SSER 5)
. Niagara Mohawk Power Corporation shall submit an inservice inspection program in accordance with 10 CFR 5 30.55a(g)(4) for staff review by
. July 31, 1987.
- The parenthetic iotation-following the title of many license conditions denotes the section of-the Safety Evaluation Report-(SER) and/or its supplements wherein the license' condition is discussed.
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4 ATTACEMENT 4' NIAGARA MORAVK POVER CORPORATION LICENSE NO. NPF-69 DOCKET NO. 50-410 Sirppor titur Information and No Slenificant Hazardp_Qqngide[All2D By letter dated November 27, 1985 the 0,taff issued Special Nuclear Materials (SNM)-License SNM-1895 for Nine Mile Point Unit 2 (NMP2) that authorized Niagara Mohawk Power Corporation to receive, possess, inspect, and store
. uranium enriched in_the U-235 isotope contained in fuel assemblies.
In the application for the SNH license, Niagara Mohawk requested various authorizations regarding-the fuel assemblies. Niagara Mc5c;k's_SNM application stated, among other things, that the maximum 29;er of fuel assemblies allowed outside a normal, approved storage locat.on or normal
- shipping container is three (3) above the refuel floor and one (1) below the floor in the spent fuel confines. The Safety Evaluation issued in support of the SNM license identified these conditions and +he SNM license incorporated
- them as License Conditions 18 and 19.
As stated in the Safety Evaluation issued with the SNM license, the SNM license automatically terminated upon issuance of the 10 CFR $ 50 opetating
- license'for NMP2.
However, the staff = determined that specific cor.ditions in the SNM license related to the storage and handling of unirradiated fuel assemblies _also applied to operation under tne 10 CFR $ 50 operating license.
As a result, to emphasize nuclear criticality safety for fuel assemblies out of. authorized storage locations or shipping containers, the Staff conditioned the NMP2 Operating License NPF-69 by including license condition 2.C.(S)b.
SSER-4, Section 9.1, discusses this condition and its basis.
After a review of pertinent NMP2 licensing. documents concerning License
_ Condition 2.C.(3)b, Niagara Mohawk believes this 11coase condition should be amended because, in ite nresent wording, it precludes the simultaneous use of both fuel preparation machines. This represents.a departure from normal BVR-fuel; handling; practices as described in General Electric's-(CE) SIL 152,
" Criticality Margins ~For Storage of New Fuel", March 31, 1976 and GE Technical Direction document 22A6042.
Both documents allow three e.ssemblies out of storage,'but,do not restrict location as to vhether the assemblies should-be above-or below the refueling floor.
For example:
"A fuel array of?up to three fuel bundles outside of a normal 1 storage-area or normal shipping container should-be maintained with an edge-to-edge spacing of 12 inches or more from all other fuel" (SIL No. 152,. Procedural Reevmmendations for Normal-Fuel Handling Operations,_ item-3),
a "A fuel array of up to three fuel-bundles or assemblies outside of.
a storage area or shipping container must maintain an edge-to-edge spacing of 12 inches or more from all other fuel" (CE 22A6042,.section 10.2.2.b(3)).
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L "A fuel array of four or more fuel bundles outside cf the normal fuel storage areas or' properly designed fuel shipping container should be prohibited" (SIL No. 152, Procedural Recommondations for Normal Fuel Handling Operations, item 4).
x "A fuel array of four or more fuel bundles or assemblies outside of-the fuel storage areas or fuel shipping container-is prohibited" (GE 22A6042, section 10.2.2.b.(4)).
- "No more than two fuel bundles should be allowed in or around a fuel prep machine at any time. This fuel should be separated from the main body of stored fuel by at least 12 inches" (SIL No. 152, Procedural Recommendations for Normal Fuel Handling Operations, item 12).
"No more than two fuel bundles or assemblies are allowed around a fuel prep machine with_ fuel inside the prep machine, or a total of three fuel bundles or assemblies at any time.
Around is defined as leaning adjacent to the fuel prep machine or pool vall adjacent to the machine. -This fuel should be separated from the fuel storage-racks by greater than 12 inches" (GE 2246042, section 10.2.2.b.(7)).
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Additionally, GE.22A6042 provides instructions for receiving nuclear fuel and loading reload-fuel in BVRs.
Section 4.6.3 or GE 22A6042 states:
4.6;3 Channglinc and DeshaDARMDg_Jn the Fuel-Storare Pool.
~A section of the fuel storage pool is used for channeling and dechanneling operations, and two fuel preparation machines are provided for this purpose. The use of two machines permits simultaneous removal of channels from irradiated fuel bundles and installation.of such-reusable channel on nev (unirradiated) fuel bundles. A fuel preparation machine may also be used to install a new channel on a new fuel bundle.
~ Fuel bundles avaiting channeling or dechanneling are stored in fuel storage racks in the pool and transported to_and-from the' fuel preparation machines by means of the refueling platform and-fuel grapple. Refer to Appendix 10 for a listing'of the procedural requirements for normal. fuel handling operations.
Finally, License Condition 2.C.(3)b is also inconsistent with-NMP2 USAR Section 9.1.4.2.11, which describes rechanneli g of fuel using both fuel prep machines. Niagara Mohawk proposes 1 the license amendment, as' identified in Attachment A, to provide consistency with the guidance contained in these documents and' operational flexibility during refueling operations.
.The proposed changesLto the license vill not alter the limitations on fuel
-handling.above-.the refuel floor.--License condition 2.c.(3) currently permits-up to three assemblies above the refuel floor-outside approved storage locations,-and that provision is-rettined in the proposed revision;
- However, "the allowed number._of assemblies below the refueling floor outside approved
- storage-locations vill-increase from one to three. General Electric has performed calculations demonstrating that four fuel assemblies in any cor. figuration-vill' remain-suberitical in the fuel pool, provided a minimum
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,4 distance-of 12 inches is maintained _between these four assemblies and any-1 surrounding assemblies. The proposed change limits the number of assemblies j
outside' approved locations to three, and requires that a 12-inch spacing be maintained around the three assemblies. Therefore, fuel handling in-accordance with-the_ proposed amendment vill not result in an inadvertent criticality.-
Compliance with the proposed license conditions is maintained by the-following:
Supervision of all fuel movements by appropriately licensed-Senior Reactor Operators per Technical Specification 6.2.2.f.
Training of licensed fuel handlere as required by Technical Specification 6.4 and ANSI /ANS-3.1-1978.
Use of_ approved procedures governing refueling operations per Technical Specification 6.8.1.c.
-The design of new fuel and spent fuel storage facilities, Therefore, adequate assurance exists that any fuel movement vill be.in accordance with the proposed license provisions and consequently vill not create the possibility of an inadvertent criticality in the fuel pool.
10 CFR $ 50.91 requires _that at the time a licensee requests an amendment, it i
mustDprovide to the Commission its analysis, using the standards in Section 50:92, about the issue of no significant hazards consideration.
Therefore, in accordance with 10 CFR $ 50.91 and 10 CFR 5 50.92, the following analysis has been performed:
-The operation of Nine Mile Point Unit 2 _in accordance with the proposed t
gmsndment, vill not involve a significant-increase in the DI2hability or
=consecuences of an accident previqngly evaluated.
The proposed license amendment increases the number of fuel assemblies inLthe-spent. fuel pool, allowed out of approved storage locations, from one to three.
However, analyses have been performed demonstrating that no four assemblies in any configuration can be made critical, provided a 12 inch spacing bc veen assemblies is maintained.
Vith a limit of three assemblies out of their b
. storage locations at any one time a criticality event cannot occur.
Administrative and procedural controls assure complim. e with the license.
condition.
Thus, this amendment does not affect the probability of a criticality and/c, a radiological event.
The proposed _ chance of license' condition 2.C.(3)c from "four" to "three" fuel assemblies merely reflects the proposed change in_ License Condition 2.C.(3)b and maintains consistency,- This change is administrative in nature and does Enot affect the probability or consequences of any accident, Therefore, operation in accordance with the proposed amendment vill not involve any L ncrease inLthe probability or consequences of'an accident previously i
evaluated.-
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i z1he operation of-Nine hile Point Unit 2. in attardance with the_ proposed amendment, vill not create the_Raffibility of a_nev or different kind _pi
. accident from any accident Dr.1Y12M11v evaluated.
The Staff's Safety Evaluation dated November 27, 1985, issued in support of
-Special Nuclear Materials License No. SNH-1895 for NMP2 states, on page 6, that_" Calculations-have-indicated-that three assemblies out of storage cannot be made critical under any conditions." Other General Electric calculations have indicated that four assemblies out of storage cannot be made critical under any conditions.' Thus, increasing the number of fuel assemblies allowed out of their shipping' containers-or storage racks to three vill not create a criticality concern.
JThe proposed change of license condition 2.C.(3)c from "four" to "three" fuel assemblies merely reflects the proposed change in License condition 2.C.(3)b and maintains consistency. This change is administrativ.* in nature and does not. alter any. fuel handling requirements. Therefore, operation in accordance with the' proposed amendment will'not create the possibility of a new or different kind of accident from any accident previously evaluated.
The opgration of Nine Hi3e Point Unit 2. in accordance v.lth the proposed agendment _ vill not involve a significant reduction in a margin of safety.
The proposed license amendment does not change any of the requirements contained in Technical' Specification Limiting Conditions for Operation and Surveillance Requirements or affect any of their assumptions or bases.
All fuel movement vill still be'in accordance vith the Administrative Controls contained-in.the Technical Specifications, therefore assuring compliance with the proposed-amendment. Calculations have demonstrated that up to four bundles in arg configuration cannot be made critical, therefore-compliance with the' proposed amendment provides adequate margin against an inadvertent criticality.
The proposed-change'of License condition 2.C.(3)c from "four" to "three" fuel assemblies merely reflects:the proposed-change in License Condition 2.C.(3)b and maintains consistency. ~Therefore, operation of Nine. Mile Point Unit 2, in addition with the proposed amendment, vill not involve-a significant reduction in a margin-of safety.
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