ML18041A121
| ML18041A121 | |
| Person / Time | |
|---|---|
| Site: | 07002948 |
| Issue date: | 11/27/1985 |
| From: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Mangan C NIAGARA MOHAWK POWER CORP. |
| Shared Package | |
| ML18041A122 | List: |
| References | |
| NUDOCS 8512090457 | |
| Download: ML18041A121 (50) | |
Text
NOY 27 1985
~~i'.~ W ) ))5 P Q2 FCUP:MLH 70-2948 Niagara Mohawk Power Corporation ATTN:
Mr. C. V. Mangan Senior Vice President 300 Erie Boulevard West
- Syracuse, New York 13202 Gentlemen:
Enclosed is the Nuclear Regulatory Commission (NRC) Special Nuclear Materials License No. SNM-1895, which has been revised in its entirety.
This license authorizes the receipt, possession, inspection, and storage of uranium enriched in the U-235 isotope contained in fuel assemblies.
Activities authorized prior to this revision were the receipt, storage and installation in the reactor
- vessel, and preoperational testing of neutron detectors which contain uranium enriched in the U-235 isotope.
All materials are for eventual use at Nine Mile Point Nuclear Station, Unit 2.
In addition, the license authorizes the packaging of fuel assemblies and neutron detectors for delivery to a carrier for transport.
This latter authority enables you to return fuel assemblies and neutron detectors to
~ another location, e.g., return to the manufacturer.
The delivery of the assemblies to a carrier must be in accordance with 10 CFR Part 71, "Packaging and Transportation of Radioactive Material," copy enclosed.
Your attention is directed to 10 CFR 71. 12(b) of Part 71 which provides a general license under specified conditions for the use of certain shipping packages which have been licensed for use by another licensee.
Also enclosed are six copies of Amendment No.
15 to Indemnity Agreement No.
B-36, for your review and acceptance.
Please return one signed copy.
The NRC uses an electronic data processing system to record the location, by
- licensee, of special nuclear material.
The system uses a three-letter Reporting Identification Symbol (RIS) to identify licensees who submit material transfer reports and periodic material status reports in accordance with 10 CFR Part 70.53 and 10 CFR Part 70.54 of the Commission's regulations.
For this purpose, you should continue to use the RIS:
XZU, previously assigned to you.
The symbol is to be used in completing the transfer reports and the periodic material status reports and should be used in any other correspondence with the NRC relative to such reports.
You should also note the requirements of 70.51(b),
(c), and (d) regarding records, material control, accounting procedures, and physical inventories.
Your cooperation will be appreciated.
Your application requested an exemption from the provisions of 10 CFR Part 70.24.
Such an exemption would relieve you from the requirements of having a criticality
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alarm system.
Because of the inherent features associated with the storage and inspection of unirradiated fuel and the neutron detectors, the NRC staff has determined that you have shown good cause for being granted the exemption, that such exemption is authorized by law, and that granting such an exemption will not endanger life or property or the common defense and security and is other-wise in the public interest.
The license conditions were discussed with your Mr. D. Hill and Mrs. Merri Horn of my staff.
This license is issued following the preparation of an Environmental Assessment related to the proposed "action.
Based on this Assessment, a Finding of No Significant Impact has been prepared and approved pursuant to 10 CFR Part 51.
Copies of this Finding, which was pobiished in the Federai
~Re ister on November 8, 1985, and the supporting Environmental Assessment are enclosed:
Also enclosed is our Safety Evaluation Report in support of this license.
Sincerely, ORIGINAL SIGNED BY GLENN A.
TERRY 2.
3.
5.
6.
Enclosures:
1.
Special Nuclear Materials License No.
SNM-1895, revised in its entirety 10 CFR Part 71 Indemnity Agreement No. B-36 (six copies)
Finding of No Significant Impact Environmental Assessment Safety Evaluation Report
. T. Crow, Acting Chief Uranium Fuel Licensing Branch Division of Fuel Cycle and Material Safety, NMSS DISTRIBUTION (Docket Nos.
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NRC Form 374 ts-84)
U.
CLEAR REGULATORYCOMMISSION MATERIALSLICENSE E
1 3
OF PAGES Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of Federal Regulations, Chapter 1, Parts 30, 31, 32, 33, 34, 35, 40 and 70, and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and special nuclear material designated below; to use such material for the purpose(s) and at the place(s) designated below; to deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.
Licensee Niagara Mohawk Power Corporation Central Hudson Gas and Electric Corporatio Long Island Lighting Company New York State Electric and Gas Corporatio Rochester Gas and Electric 2l 300 Erie Boulevard West
-"Syracuse, New York 13202
- 3. License number
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- 4. Expiration"da'te November 30, 1990, or*
- 5. Docket or Reference No. e'0 2948 COPY SNM-1895, revised in its entirety
- 6. Byproduct, source, and/or special nuclear material
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A.
Uranium enriched in the U-235 isotope I~
A. (2800 kg of U-'~235 in
,uranium en-
-"-<<;.:b.l
~==g;:b.l ies
- 7. Chemical and/or physical
~. Maximum amount that licensee form Qmay possess at any one time
~under this license EtA.~-;Inl unii radi ated~~~
'." "-'- reactor fuel assem=
)
EEI B.
Uranium enriched in '-
,the U-235 isotope i~ B-.'.i'Contaaned<an scale
'neutron de'tectojs'.j E. l~
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'i'ched to no
~more than 3.05 w/o in U-235 B.~One (1) gram
.,~~2 of U-235 at any enrichment 9.
Authorized Use 5r The materials are for use in accordance with s'tatements, representations, and conditions specified in the licensee's application dated March 23,
- 1982, and its supplements dated April 17, May 1, June 12, September 27, October 22, October 29, and November 18, 1985.
- 10. Authorized Place of Use The licensee's Nine Mile Point Nuclear Station, Unit 2, located in the Town of Scriba, Oswego County, New York, as described in the aforesaid application.
ll. The minimum technical qualifications for the General Superintendent Nuclear Generation shall be in accordance with Section 4.2.1, "Plant Manager,"
Upon conversion of Construction Permit No. CPPR-112 to an operating license, whichever
. is earlier.
NRC Form 374A I5 84)
U.S NUCLE REGULATORYCOMMISSION MATERIALSLICENSE SUPPLEMENTARY SHEET Ueense number SNM-1895 Docket or Refcrcnec number 70-2948 C
AGE 2
oF PAGES 12.
13.
14.
15.
16.
17.
18; The minimum technical qualifications for Station Superintendent shall be in accordance with Section 4.2.1, nPlant Manager,"
The minimum technical qualifications for the Reactor Analyst Supervisor shall be in accordance with Section 4.4.1, "Reactor Engineer,"
tl4 ~~
proper fuel handling pry'ure's encl.u of the activities.
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hi~<related health>and safety aspects i!//f//
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Fuel assemblies, wheAtorednd,the.i h pp' ontaj,ners, shal'1-be stacked no more than three conte>>ners@>>gh.
/,:jg!,tIIj
+j/'::I Cf; All fuel assemblies sha'41+be in their sh'lpp<ing con'ta'iners,o'. storage racks in the New Fuel Vault or in the Spent>Fuel Storage Faci"lity except
.forJ the following:
a.
No more than three assemblies/chal,l be allowed>above the refueling floor.
b.
No more than one fuel assembly shall be below the refueling floor outside the storage racks.
The minimum technical qualifications for the Superintendent of Chemistry and Radiation Management shall be in accordance with the requirements for "Radiation Protection Manager," Regulatory Guide 1.8, September 1975.
The minimal technical gualificat>>org'gS.'ed'upervipor of Chemistry and Radiation Protection shall be in accorga~cemith the requiremeqts for "Radiation Protection Manager",Regulatory Guid 1~8, September 1975.
The following training 4sha 1
be completed by each individua'1~prior to participation in the radiation safety angl'uel handling programs:
(a) All radiation sleety perMon 1~involved in fuel~gandling s'hall be trained in radiation safety and in MM "~s+Undt ~zdiationKprotection,procedures related to fuel assembly healing.
(
(b) All o erations ersonne invol.
d
~Muel ha lan shall receive trainin in
- 19. The above four fuel assemblies shall maintain a minimum edge-to-edge spacing of twelve (12) inches from the shipping container array and approved storage rack locations.
- 20. All preoperational testing of fuel handling equipment shall be completed prior to use for handling the new fuel shipment.
- 21. The New Fuel Storage Vault shall have no more than 10 fresh fuel assemblies uncovered at any one time.
- 22. The licensee is hereby exempted from the provisions of 10 CFR 70.24 insofar as this exemption applies to materials held under this license only.
- 23. Records of the weekly visual surveillance of the shipping containers with the neutron detectors shall be maintained and a copy of each surveillance submitted to the Superintendent Chemistry and Radiation Management and the Nine Mile Point, Reactor'nalyst Supervisor.
copY ur id
1
NRC Form 374A (5 84) d I
U.S. NUCLE > REGULATORYCOMMISSION MATERIALSLICENSE SUPPLEMENTARY SHEET License number SNM-1895 Docket or Refcrcnce number 70-2948 OF PAGES
- 24. The licensee shall repackage fuel in accordance with 10 CFR Part 71 prior to delivery to a carrier for transport.
- 25. Procedures for the handling and installation of the neutron detectors in the reactor vessel shall be approved by the Superintendent, Chemistry and Radiation Management.
26.
A member of the Chemistry and Radiation Management staff shall be present during all neutron detector handling operations and shall monitor these activities.
27.
The licensee shall maintain records of themyLtamination survey (smear survey) results for both the neutron detector con4~1seeYs and~M~ue3 assembly shipping crates.
- 28. The licensee shall maintain@ed fully implement all provjsjons of the Commission approved Physical Security+~ lan, including changes made pursuant to the authority of 10 CFR 70.32(e).
The approved Security Plan is titled nNi~e ile Point Nuclear Station Unit II2, Security,Plan for Special Nuclear Material of/Low Strategic Significance, Revisionrg" djted August 1985.
The Physac~ag Setgu ity Plan shall. be withheld from publidgisclosgjd suant to 18 CFR
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NUCLEAR R GULA RY C MMISSI N
Date:
ORIGINAL SIGNED BY GLENN A.
TERRY By FOR WE T ~
CROW l p7/
Division o Fuel Cycle an Material Safety, NMSS Washington, D.C.
20555
NOV 8 7 1985 DOCKET NO:
APPLICANT:
70-2948 Niagara Mohawk Power Corporation Central Hudson Gas and Electric Corporation Long Island Lighting Company New York State Electric and Gas Corporation Rochester Gas and Electric FACILITY:
SUBJECT:
Nine Mile Point Nuclear Station (NMP), Unit 2 SAFETY EVALUATION REPORT -
REVIEW OF LICENSE APPLICATION DATED JUNE 12,
- 1985, AND SUPPLEMENTS THERETO DATED SEPTEMBER 27, OCTOBER 22, OCTOBER 29, AND NOVEMBER 18, 1985 I.
INTRODUCTION A.
Genena1 By application dated June 12,
- 1985, and supplements dated September 27, October 22, October 29, and November 18,
- 1985, Niagara Mohawk, acting on its own behalf and as agent for the above co-owners, requested an amendment to its License No.
SNM-1895 to authorize the receipt, possession, inspection, and storage of fuel assemblies containing uranium enriched up to 3.05 w/o.
The present license only authorizes the receipt, storage and installation in the reactor vessel and preoperational testing of neutron detectors.
The fuel assemblies will be supplied by General Electric Corporation.
Each fuel assembly contains 62 fuel rods and 2 nonfuel rods called water rods.
The rods are spaced and supported in a square 8XB array, by the upper and lower tie plates, and by 7 fuel spacer grids.
Table 1 gives general fuel rod parameters that describe the fuel that wi.l,l eventually be used at Nine Mile Point, Unit 2.
The materials license was requested to allow early receipt of the fuel for reactor loading.
The license will automatically terminate upon issuance of the Part 50 operating license for Unit 2.
Table 1
Parameters Fuel Assembly Data:
Overal 1 Length 176. 16" Nominal Active Fuel Length 150.0" Fuel Rod Pitch 0.640" Rod Array 8X8 Rods/Assembly 64 (includes 2 water rods)
Fuel Rod Data:
Fuel Pellet Material Clad Outside Diameter U02 + U02/Gd203 0.483"
Niagara Mohawk Power Corporation NOV 2'7 1985 Table 1
(CONTINUED)
Clad Thickness Clad Inside Diameter Fuel Pellet Immersion Density Fuel Pellet Diameter Maximum Pin Enrichment Maximum quantity U-235 0.032" 0.419" 95.0X theoretical 0.410" 3.05 w/o U-235 4.01 kg U-235/183.2 kg U 8 2.19 w/o BE Location Descri tion The NMP, Unit 2, is a Boiling Water Reactor located on the southwest shore of Lake Ontario in Oswego County, New York.
The construction permit, CPPR-112, was issued in June 1972 (Docket No. 50-410).
II.
AUTHORIZED ACTIVITIES The applicants'equest authorization to receive,
- possess, and store 800 finished fuel assemblies with a maximum pin enrichment of 3.05 w/o in U-235.
Fuel assem-blies will be stored in the New Fuel Storage Facility and/or the Spent Fuel Storage Facility in the Reactor Building.
The designated fuel storage areas in each are the New Fuel Storage Vault in the New Fuel Storage Facility and the Spent Fuel Storage Pool racks in the Spent Fuel Storage Facility.
The fuel assemblies, in their shipping containers, will be temporarily stored in the receiving area and on the refueling floor.
The applicants also request authori-zation to repackage any assembly, if necessary, for delivery to a carrier.
It should be noted that the license does not authorize insertion of a fuel assembly into the reactor vessel.
The licensee is currently authorized to receive, store, install, and pretest neutron detectors.
III.
SCOPE OF REVIEW The safety review of the Niagara Mohawk request for a materials license amend-ment includes an evaluation of Nine Mile Point s organization, administration, nuclear criticality safety, radiation protection, physical security, and fire protection programs.
During the review,.discussions were held with the NRR Project Manager, the Resident Inspector, Region I, and with staff members of the applicant.
The NMP Security Plan was evaluated by the Safeguards Material Licensing and International Activities Branch, Division of Safeguards, Office of Nuclear Material Safety and Safeguards.
IV.
POSSESSION LIMITS Conditions 6, 7, and 8 of the license specify the type, form, and quantity of material the licensee may possess at any one time under this license and shall read as follows:
Niagara Mohawk Power Corporation NOY 2 7 1985 6.
Material 7.
Form 8.
~uaatit A.
Uranium enriched in the U-235 isotope B.
Uranium enriched in the U-235 isotope V.
ORGANIZATION A.
In unirradiated reactor fuel assem-blies B.
Contained in sealed neutron detectors A.
2800 kg of U-235 in uranium en-riched to no more than 3.05 w/o in U-235 B.
One (1) gram of U-235 at any enrichment A.
Nucl ear,Cri tica 1 it Sa fet and Radiation Protection Res ons ibi 1 ities 1.
General Superintendent Nuclear Generation The General Superintendent is directly responsible for the safe and efficient operation of the plant and its equipment.
He is responsible for compliance with all NRC regulations and license conditions.
2.
Station Superintendent All receipt,
- shipment, and internal transfer of special nuclear material in the form of fuel assemblies will be performed in accordance with approved fuel handling procedures, under the control of the Station Superintendent.
He is responsible for preparation and approval of fuel handling procedures.
3.
Reactor Analyst Supervisor The Reactor Analyst Supervisor approves the fuel handling procedures.
He provides guidance for fuel management and maintains performance and fuel accountability records.
4.
Superintendent of Chemistry and Radiation Management The Superintendent of Chemistry and Radiation Management (Radiation Protection Manager - RPM) is responsible
.for establishing the Health Physics Program and developing health physics procedures for NMP-2 that are designed to assure compliance with applicable regulations,
- licenses, and regulatory guides.
In
, addition, he provides technical guidance for conducting this program, audits the effectiveness and the result of the program, and modifies it as required.
5.
Supervisor of Chemistry and Radiation Protection The Supervisor of Chemistry and Radiation Protection is responsible for conducting the Health Physics Program for NMP, Unit 2.
His duties include the training of personnel in radiation safety, control of radiation exposures to personnel to maintain exposure levels that are as low as reasonably achiev-able, to continuously evaluate and review the radiological status of the
- station, and to make recommendations for control or elimination of radiation hazards.
Niagara Mohawk Power Corporation
'OV 87 198S B.
Minimum ual ifica tions The qualifications of the aforementioned personnel have been reviewed and the staff finds they meet the minimum qualifications specified in Regulatory Guide 1.8, "Personnel Selection and Training" or ANSI/ANS 3. 1-1978, "Selection and Training of Nuclear Power Plant Personnel" or both; however, the applicants have not clearly specified minimum qualifications for these positions.
Accord-ingly, Condition Nos.
11-15 are recommended to correct this deficiency and shall read as follows:
Condition 11.
The minimum technical qualifications for the General Superintendent Nuclear Generation shall be in accordance with Section 4.2.1, "Plant Manager,"
Condition 12.
The minimum technical qualifications for Station Superinten-dent shall be in accordance with Section 4.2. 1, "Plant Manager,"
Condition 13.
Condition 14.
Condition 15.
The minimum technical qualifications for the Reactor Analyst Supervisor shall be in accordance with Section 4.4.1, "Reactor Engineer,"
The minimum technical qualifications for the Superintendent of Chemistry and Radiation Management shall be in accord-ance with the requirements for "Radiation Protection Manager," Regulatory Guide 1.8, September 1975.
The minimal technical qualifications for the Supervisor of-Chemistry and Radiation Protection shall be in accordance with the requirements for "Radiation Protection Manager,"
Regulatory Guide 1.8, September 1975.
C.
~Trainin Training is conducted to ensure that all personnel involved in fuel handling participate in a formal training program.
The overall training program for the plant staff is the responsibility of the General Superintendent Nuclear Genera-tion.
All persons entering the restricted area of the station receive training pursuant to 10 CFR 19. 12.
This training is the responsibility of the Supervisor of Chemistry and Radiation Protection.
Radiation Protection Technicians receive training in the use of equipment and procedures for dealing with radiological concerns and job-related accidents.
All personnel involved in fuel receipt receive basic training in radiation protection and the site emergency plan.
In order to ensure that all persons involved in fuel handling receive training in all fuel handling operations, the staff recommends that License Condition 16 be added to supplement Niagara Mohawk's training program.
Condition 16.
The following training shall be completed by each individual prior to participation in the radiation safety and/or fuel handling programs:
l
Niagara Mohawk Power Corporation NOV 2'7 198S (a)
All radiation safety personnel involved in fuel handling shall be trained in radiation safety and in NMP's Unit 2, radiation protection procedures related to fuel assembly handling.
(b)
All operations personnel involved in fuel handling shall receive training in proper fuel handling procedures, including the related health and safety aspects of the activities.
D.
Administrative Procedures Procedures for the control and handling of nuclear fuel are reviewed by the Chemistry and Radiation Management and Operations departments.
These procedures are approved by the General Superintendent, the Station Superintendent, and the Reactor Analyst Supervisor.
The Superintendent of Chemistry and Radiation Management establishes the Health Physics Program and develops the health physics procedures for NMP-2.
The Supervisor of Chemistry and Radiation Protection is responsible for conducting the Health Physics
- Program, and the Radiation Protection Technicians perform the required radiation monitoring and exposure control work in accordance with radiation protection instructions prepared by the Radiation Protection Supervision.
VI. NUCLEAR CRITICALITY SAFETY A.
General The fuel assemblies will be stored in their shipping containers in the fuel receiving area, on the refueling floor, in the New Fuel Storage Vault, and in the Spent Fuel Storage Facility of the Reactor Building.
The New Fuel Storage racks can accommodate up to 270 new fuel assemblies utilizing all storage rack positions.
The Spent Fuel Storage Pool racks have positions for approximately 4,000 fuel assembly storage spaces.
In both the New Fuel Storage Vault and the Spent Fuel Storage Facility, spaces between the fuel storage positions are designed so it is not possible to insert a fuel assembly in any array position not intended for fuel.
B.
Shi in Containers The fuel assemblies may be temporarily stored in their shipping containers on the refueling floor of the Reactor Building and in the fuel receiving area.
On the refueling floor, the assemblies will be stored in their inner metal containers only, i.e., without their wooden overpacks.
Niagara Mohawk requests authorization to store fuel assemblies in these containers in arrays stacked up to three high.
The staff has previously confirmed the nuclear criticality safety of an infinite shipping container storage array stacked 3 high*.
Accordingly, the staff recommends the following condition for emphasis:
- Reference Amendment No.
5 to General Electric's Materials License No.
SNM-1097, dated June 6, 1978, Docket No. 70-1113.
Niagara Mohawk Power Corporation HOV 27 1985 Condition 17.
Fuel assemblies, when stored in their shipping containers, shall be stacked no more than three containers high.
The applicants'pplication states that no more than four fuel assemblies will be out of their containers or storage rack locations at a given time.
A maxi-mum of three assemblies will be above the refueling floor and the fourth assembly shall be below the refueling floor in the Spent Fuel Pool confines.
Calcula-tions have indicated that three assemblies out of storage cannot be made critical under any conditions.
In addition, the applicants are committed to maintaining a minimum edge-to-edge distance of >12 inches between fuel assem-blies out of storage and fuel assemblies in their shipping container array and the storage rack arrays.
It is recommended that the following conditions be added to emphasize nuclear criticality safety for fuel assemblies out of authorized storage locations or shipping containers by:
(1) limiting the number of fuel assemblies out of approved storage locations, and (2) maintaining
.a minimum edge-to-edge distance between fuel out of storage and from all other fuel.
Condition 18.
All fuel assemblies shall be in their shipping containers or storage racks in the New Fuel Vault or in the Spent'uel Storage Facility except for the following:
a.
No more than three assemblies shall be allowed above the refueling floor.
b.
No more than one fuel assembly shall be below the refueling floor outside the storage racks.
Condition 19.
The above four fuel assemblies shall maintain a minimum edge-to-edge spacing of twelve (12) inches from the ship-ping container array and approved storage rack locations.
In order to be sure the fuel handling equipment is ready to safely handle the fuel assemblies, the applicants have stated that prior to use for handling new fuel, preoperational testing of fuel handling equipment will be performed in accordance with approved procedures.
To emphasize the applicant's commitment and to ensure testing prior to use, the following condition has been added:
Condition 20.
All preoperational testing of fuel handling equipment shall be completed prior to use for handling the new fuel shipment.
D.
New Fuel Stora e Vault The New Fuel Storage Vault has the capacity to provide dry storage for 270 channeled and/or unchanneled new fuel assemblies.
The vault contains 27 sets of racks constructed of aluminum guidetubes.
Each storage rack provides support
Niagara Mohawk Power Corporation NOV 8 V 1985 and storage for a row of 10 fuel assemblies.
The minimum center-to-center spacing for fuel assemblies between rows is 11 inches.
The minimum center-to-center spacing within rows is 7.00 inches.
Criticality analysis of the above new fuel storage vault indicates it can be made critical at optimum water density moderation.
To maintain criticality safety of the New Fuel Storage Vault, the applicants propose to eliminate sources of water moderation from the New Fuel Stoi age Vault.
This is accom-plished by the presence of 32 aluminum cover plates over the new fuel assembly racks.
Each cover plate covers 10 fuel assemblies.
Administrative controls limit the maximum number of fuel assemblies that will be uncovered at any one time to 10.
The staff has determined that 10 fresh fuel assemblies in a single row, based upon the above spacing between fuel assemblies, cannot be made critical under any degree of water moderation.
It is recommended that the following license condition be added to highlight the importance of having only a maximum of 10 fresh fuel assemblies uncovered at any one time in the New Fuel Storage Vault.
Condition 21.
The New Fuel Storage Vault shall have no more than 10 fresh fuel assemblies uncovered at any one time.
E.
S ent Fuel Stora e Pool The spent fuel storage racks are composed of a honeycomb array of identical stainless steel cells.
The cells are spaced on a 6. 180 inch center and are lined with
- 0. 110-inch thick stainless steel.
Each cell has an inside clearance of 5.854 inches to accommodate an 8X8 fuel assembly channeled in 0. 100-inch thick zircaloy.
Subcriticality of the spent fuel storage pool is maintained by the presence of neutron poison sheets (Boraflex) placed on all four sides of each storage cell.
In addition, in the east west direction, each storage rack has a sheet of neutron poison placed between it and the adjacent rack.
In the north south direction, a
3-inch water gap having an equivalent effect is present between adjacent storage racks.
The staff has reviewed the applicant's quality assurance program to ensure that the neutron poison meets design specifications and is positioned securely to the walls of the storage cells.
The program was found to be adequate.
An independent nuclear criticality safety analysis of the spent fuel storage pool performed by the staff indicates a k-infinity of 0.91 for an infinite array of fresh fuel assemblies at an enrichment of 3.05 wlo U-235 and at full water density (optimum moderation).
Therefore, the array is safe.
F.
Exem tion from 10 CFR Part 70.24 The applicants have requested, pursuant to 10 CFR 70.24 (d), an exemption from the provisions of 10 CFR 70. 24.
Because the assemblies are handled as discrete
- items, they are stored with engineered controlled spacing, they are normally stored dry (cannot be made critical independent of quantity),
and even under accident conditions involving flooding with water, administrative controls limit the number of assemblies that can be moderated at one time.
The limited
Niagara Mohawk Power Corporation NOV 2 V 1985 quantities of sealed incore monitoring detectors cannot be made critical under any conditions.
Therefore, the staff determines that granting such an exemption will not endanger life, property, or the common defense and security, is other-wise in the public interest, and is authorized by law.
The staff recommends that pursuant to 10 CFR 70.14, Condition 22 shall read as follows:
Condition 22.
The licensee is hereby exempted from the provisions of 10 CFR 70.24 insofar as this exemption applies to materials held under this license only.
VII. RADIATION SAFETY All the materials requested in this application are sealed or contained sources.
Therefore, the potential for generating airborne radioactivity from the material is minimal and the principal pathway for radiation exposure to an individual is via the external radiation.
Personnel external exposures are monitored as required by 10 CFR 20.202.
This is done by using thermoluminescent dosimeters, film badges, and self-reading pocket dosimeters.
The external radiation dose to personnel is determined on a daily basis by means of self-reading pocket dosimeters.
Personnel monitoring badges (film badges and TLD's) are processed at least twice per month.
Records of radiation exposure historv and current occupational exposure are maintained for each individual for whom personnel monitoring is required.
Portable radiation survey and monitoring instruments for routine use are calibrated quarterly.
Proofs of calibration are also maintained.
Neutron exposure is monitored in accordance with Regulatory Guide 8. 14 through the use of dose rate/stay time calculations or neutron/gamma dose rate ratios.
The staff has concluded that the Nine Mile Point, Unit 2, Health Physics Program is adequate for the protection of Nine Mile Point, Unit 2 personnel, the public, and the environment.
Condition Nos. 11-l5 of the original license are to be incorporated into the revised license as Condition Nos. 23-27.
These conditions were discussed in the Safety Evaluation Reports (related to the original license) dated April 19,
- 1982, and May 8, 1985.
Condition 23.
Records of the weekly visual surveillance of the shipping containers with the neutron detectors shall be maintained and a copy of each surveillance submitted to the Superin-tendent Chemistry and Radiation Management and the Nine Mile Point, Reactor Analyst Supervisor.
Condition 24.
The licensee shall repackage fuel in accordance with 10 CFR Part 71 prior to delivery to a carrier for transport.
Condition 25.
Procedures for the handling and installation of the neutron detectors in the reactor vessel shall be approved by the Superintendent, Chemistry and Radiation Management.
I
Niagara Mohawk Power Corporation NOV 27 1985 Condition 26.
A member of the Chemistry and Radiation Management staff shall be present during all neutron detector handling operations and shall monitor these activities.
Condition 27.
The licensee shall maintain records of the contamination survey (smear survey) results for both the neutron detector containers and the fuel assembly shipping crates.
VIII.
ENVIRONMENTAL PROTECTION The Final Environmental Statement related to the operation of Nine Mile Point, Unit 2, dated May 1985 has been prepared and issued by the NRC as NUREG-1085.
An environmental assessment has also been prepared for the 10 CFR Part 70 Fuel Storage License in accordance with 10 CFR 51.21.
This assessment supports a
Finding of No Significant Impact which was published in the Federal
~Re ister on November 8, 1985.
IX.
FIRE SAFETY There is a manual fire fighting system in the New Fuel Storage Vault.
Dry chemical or CO~ and halon fire extinguishers are provided and the area is nor-mally free of combustible material.
- However, hose stations are provided for fighting fires which could occur in the fuel receiving area.
Training and administrative controls will preclude the fire fighting crews from using the hose stations to spray water into the new fuel vault or from spraying the fuel receiving areas if new fuel is being transferred from the shipping container to its storage location.
The staff has concluded that the Nine Mile Point, Unit 2 Nuclear Station, fire protection measures are adequate for the facility.
X.
PHYSICAL PROTECTION The Division of Safeguards,
- NMSS, has reviewed Niagara Mohawk's Physical Security Plan and has determined that it meets the requirements of 10 CFR 73.67.
To ensure that the Physical Security Plan shall be fully implemented and remain in effect whenever fresh fuel is stored onsite, the staff recommends Condition 28.
Condition 28.
The licensee 'shall maintain and fully implement all pro-visions of the Commission approved Physical Security Plan, including changes made pursuant to the authority of 10 CFR 70.32(e).
The approved Security Plan is titled "Nine Mile Point Nuclear Station Unit //2, Security Plan for Special Nuclear Material of Low Strategic Significance, Revision 1
" dated August 1985.
The Physical Security Plan shall be withheld from public disclosure pursuant to 10 CFR 2.790(d).
XI.
CONCLUSIONS 1.
After reviewing the application and its supplement, the staff finds that:
a.
The application meets the requirements of the Atomic Energy Act, as
- amended, and of the regulations of the Commission,
Niagara Mohawk Power Corporation 10 NOY 2 7 1985 b.
Issuance of the license would not be inimical to the common defense and security, and c.
Issuance of the license would not constitute an unreasonable risk to the health and safety of the public.
2.
With the recommended license conditions, the NRC staff finds that:
a.
The applicants are qualified by reason of training and experience to use the material for the purpose requested in accordance with the regulations in 10 CFR 70.23.
b.
The applicants'roposed equipment and facilities are adequate to protect health and minimize danger to life or property.
c.
The applicants'roposed procedures to protect he'alth and to minimize danger to life or property are adequate.
XII.
RECOMMENDATIONS The staff recommends approval of the application and its supplements subject to the following conditions which the staff finds are appropriate to protect health or to minimize danger to life or property:
Condition 11.
Condition 12.
The minimum technical qualifications for the General Superintendent Nuclear Generation shall be in accordance with Section 4.2.1, "Plant Manager,"
The minimum technical qualifications for Station Superintendent shall be in accordance with Section 4.2. 1, "Plant Manager,"
ANSI/ANS 3. 1-1978.
Condition 13.
The minimum technical qualifications for the Reactor Analyst Supervisor shall be in accordance with Section 4.4.1, "Reactor Engineer,"
Condition 14.
Condition 15.
Condition 16.
The minimum technical qualifications for the Superintendent of Chemistry and Radiation Management shall be in accordance with the requirements for "Radiation Protection Manager," Regulatory Guide 1.8, September 1975.
The minimum technical qualifications for the Supervisor of Chemistry and Radiation Protection shall be in accordance with the requirements for "Radiation Protection Manager,"
Regulatory Guide 1.8, September 1985.
The following training shall be completed by each individual prior to participation in the radiation safety and/or fuel handling programs:
Niagara Mohawk Power Corporation NOV 2 V 1985 Condition 17.
Condition 18.
(a)
All radiation safety personnel involved in fuel handling shall be trained in radiation safety and in NMP's Unit 2, radiation protection procedures related to fuel assembly handling.
(b)
Al 1 operations personnel involved in fuel handling shall receive training in proper fuel handling procedures, including the related health and safety aspects of the activities.
Fuel assemblies, when stored in their shipping containers, shall be stacked no more than three containers high.
All fuel assemblies shall be in their shipping containers or storage racks in the New Fuel Vault or in the Spent Fuel Storage Facility except for the following:
a.
No more than three assemblies shall be allowed above the refueling floor.
.- b.
No more than one fuel assembly shall be below the refueling floor outside the storage racks.
Condition 19.
Condition 20.
Condition 21.
The above four fuel assemblies shall maintain a minimum edge-to-edge spacing of twelve (12) inches from the shipping container array and approved storage rack locations.
All preoperational testing of fuel handling equipment shall be completed prior to use for handling the new fuel shipment.
The New Fuel Storage Vault shal 1
have no more than 10 fresh fuel assemblies uncovered at any one time.
Condition 22.
The licensee is hereby exempted from the provisions of 10 CFR 70.24 insofar as this exemption applies to materials held under this license only.
Condition 23.
Records of the weekly visual surveillance of the shipping containers with the neutron detectors shall be maintained and a copy of each surveillance submitted to the Superin-tendent Chemistry and Radiation Management and the Nine Mile Point, Reactor Analyst Supervisor.
Condition 24.
The licensee shall repackage fuel in accordance with 10 CFR Part 71 prior to delivery to a carrier for transport.
Condition 25.
Procedures for the handling and installation of the neutron detectors in the reactor vessel shall be approved by the Superintendent, Chemistry and Radiation Management.
4
~
Niagara Mohawk Power Corporation 12 NOV SV i98S Condition 26.
Condition 27.
Condition 28.
A member of the Chemistry and Radiation Management staff shall be present during all neutron detector handling operations and shall monitor these activities.
The licensee shall maintain records of the contamination survey (smear survey) results for both the neutron detector containers and the fuel assembly shipping crates.
The licensee shall maintain and fully implement all provisions of the Commission approved Physical Security Plan, including changes made pursuant to the authority of 10 CFR 70.32(e).
The approved Security Plan is titled "Nine Mile Point Nuclear Station Unit 02, Security Plan for Special Nuclear Material of Low Strategic Significance, Revision 1" dated August 1985; The Physical Security Plan shall be withheld from public disclosure pursuant to 10 CFR 2.790(d).
Origioai Signed BV:
Merri Horn Original Signed by Approved by:
N. Ket=3.ach T.
Crow, Section Leader Mer ri Horn Uranium Process Licensing Section Uranium Fuel Licensing Branch Division of Fuel Cycle and Material Safety, NMSS OFC: FCUP: FCUP
. FCUF: FCUF NAME:MHorkfas: NKetzl ch: VLTXarpe:
Crow DATE:ll/~g(/85: 11/ /85: ll/~+/85: 11/P /85:
OFFICIAL RECORD COPY
U.S.
NUCLEAR REGULATORY CONMISSIOH FINDING OF NO SIGNIFICANT IMPACT 7590-01 ISSUANCE OF SPECIAL NUCLEAR MATERIAL LICENSE WO. SNN-1895 NIAGARA MOHAWKS POKR CORPORATION, ET. AL; OSlKGO COUNTY, HER YORK DOCKET NO. 70-2948 The U.S. Nuclear Regul atory Commission
( the Commi ssi on) i s considering the amendment of Special Nuclear Haterial License No. SHt&1895 to permit the receipt, possession, inspection, and storage of unirradiated nuclear fuel assemblies at the Nine Nile Point Nuclear Station in Oswego County, New York.
The unirradiated fuel assetrblies will be for eventual use in the Nine Nile Point Nuclear Station (NYP), Unit 2, once its operating license is issued.
ENVIRONMENTAL ASSESSNEHT Identification of Pro osed Action The proposed action would authorize the, applicants to receive,
- possess, inspect, and store special nuclear materials in the form of unirradiated fuel assemblies.
The Heed for the Proposed Action The proposed license will allow the applicants to receive and store fresh fuel prior to issuance of the Part 50 operating license in order to inspect the fuel and to finalize fuel preparation needed to load the fuel into the reactor vessel.
Actual core loading, however, will not be authorized by the proposed license.
OFFICEi SURNAME)
DATEI NRC FORM 3I8 II0/8DI NRCM 0240 OFFICtAL RECORD COPY
- US. GPO 1983M00.2i I
Environmental Imoacts of the Pro osed Action A.
Nuclear Criticalit and Radiation Safet Once at Nine t1ile Point, Unit 2, the new fuel may be temporarily stored in shipping containers prior to placement in the designated storage locations:
the new fuel storaae vault and the spent fuel storage pool.
Previous analysis of a shipping container array stacked three hiah and of infinite extent in the horizontal plane, with no separation between containers, and independent of the degree of water moderation and/or reflection has been determined to be critically safe.
This analysis envelops the proposed NVP, Unit 2, shipping container array and thus assures nuclear criticality safety for such an array.
Upon removal of the fuel assemblies from the shipping containers, they are inspected and surveyed for any external contamination.
Assuming no contam-ination is found, the assemblies are transferred to their designated storaae location. Criticality safety in storage locations is assured by the use of engineered safeauards and administrative controls.
This is accomplished by use of neutron poisons in the spent fuel pool and by eliminating sources of water moderation in the new fuel storage vault.
Therefore, nuclear criticality safety of the storage racks is assured.
Since the fresh fuel assemblies are sealed
- sources, the principal exposure pathway is via external radiation.
For low-enriched uranium fuel U-235 enrichment),
the exposure level to an individual standina 1
from the surface of the fuel would be less than 25 percent of the
(< 4 percent foot maxi mum OFFICE)
SURNAME)
DATE)
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, the applica
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exposure as low as reasonably achievable.
Therefore, the staff has concluded, that the applicants'equested operations can be carried out with adequate radiation protection of the public and environment.
Only a small amount, if any, of radioactive waste (e.g.,
smear papers and/or contaminated package materials) is expected to be generated as a
result of fuel handling and storage operations.
Any waste that is produced will be properly stored onsite until it can be shipped to a licensed disposal facility.
B.
Transportation In the event the applicants must return the fuel to the fuel fabricator, all packaging and transport of fuel will be in accordance with 10 CFR Part 71.
Ho significant external radiation hazards are associated with the unirradiated fuel because the radiation level from the clad fuel pellets is low and because the shipping packages rrust meet the external radiation standards in 10 CFR Part 20. Therefore, shipment of unirradiated fuel by the applicants is expected to have an insignificant impact upon the environment.
OFFICE)
SURNAME)
DATEI C.
Accident Analysis In the unlikely event that an asserbly (either within or outside its shipping container) is dropped during transfer, the fuel cladding is not expected to rupture.
Even if the fuel rod cladding were breached and the pellets were released, an insignificant environmental impact would result.
The fuel pellets are conyosed of a ceramic U02 that has been pelletized
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NRC FORM 318110/801 NRCM 0240 OFFlClAL RECORD COPY
- UB. GPO 1983~00-24
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and sintered to a very high density.
In this form, release of U02 aerosol is unlikely except under conditions of deliberate grinding.
Additionally, U02 is soluble only in an acid solution so dissolution and release to the environment are extremely unlikely.
D.
Conclusion The environmental impacts associated with the handling and storage of new fuel at NHP, Unit 2, are expected to be insignificant.
Essentially no effluents, liquid or airborne, will be released, and acceptable controls will be implemented to prevent a radiological accident.
Therefore, the staff concludes that there will be no significant impacts associated with the proposed action.
Alternative to the Pro osed Action The principal alternative would be to deny the requested license.
Assuming the operating license will eventually be issued, denial of the storage only license would merely postpone new fuel receipt at Nt<P, Unit 2.
Although denial of the Special Huclear Materials License for HNP, Unit 2, is an alternative available to the Commission, it would be considered only if significant issues of public health and safety could not be resolved to the satisfaction of regulatory authorities involved.
Alternative Use of Resources This action does not involve the use of resources not previously considered in connection with the Commission's Final Environmental Statement (NUREG-1085) dated I4ay 1985, related to this facility.
OFFICE]
SURNAME]
DATE NRC FORM 318 RO/80) NRCM 0240 OFFICIAL RECORD COPY
- UD. GPO 1983~00-24
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Agencies and Persons Consulted The Corwission's staff reviewed the applicants'equest of June 12, 1985, and its amended request dated Septerrber 27, 1985, and did not consult other agencies or persons.
Finding of No Significant Intact The Comrfssion's Division of Fuel Cycle and t)aterial Safety has prepared an Environmental Assessment related to the issuance of Special Nuclear Materials License No.
SNtUI-1895.
On the basis of this assessment,'the Comission has concluded that the envi ronrental impact created by the proposed licensing action would not he significant and does not warrant the preparation of an Environmental Itlpact Statenent.
Accordingly, it has been determined that a
Finding of No Significant Impact is appropriate.
The Environt11ental Assessment and the above documents are available for public inspection and copying at the Cormission's Public Doculrent Room, 1717 H Street, HW., Iashington, DC.
Copies of the Environmental Assessment may be obtained by calling (301)427-4510 or by writing to the Uranium Fuel Licensing Branch, Division of Fuel Cycle and Vaterial Safety, U.S. Nuclear Regulatory Commission, lashington, DC, 20555.
Dated at Silver Spring, ttaryland this 4th day of FOR THE NUCLEAR R GULATORY COtNISSION Origirml Signed B71 W. X. Crov."
1985.
L T. Crow, Acting Chief Uranium Fuel Licensing Branch Division of Fuel Cycle and Hater ial Safety, NNSS FCUF g
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LICENSEE:
70-2948 Niagara Hohawk Power Corporation Central Hudson Gas and Electric Corporation Long Island Lighting Company Hew York State Electric and Gas Corporation Rochester Gas and Electric FACILITY:
SUBJECT:
h!ine Hile Point Huclear Station, Unit 2 EHVIRONHEHTAL ASSESStiEt!T - LICENSE APPLICATIOH TO RECEIVE NEI'FUEL
Background
By letter dated June 12, 1985, and as amended September 27, 1985, Hiagara mohawk, acting on its own behalf and as agent for the above co-owners, applied for an NRC license to permit the receipt, possession, inspection, and storage of special nuclear materials contained in unirradiated nuclear fuel asseirblies.
The materials are for eventual use in the Nine Nile Point tluclear Station, Unit 2. In accordance with 10 CFR 51.21, the HRC has prepared this assessoent of environnental
&@acts that riay be caused by issuing the requested license.
The proposed action is issuance of a special nuclear materials license pursuant to 10 CFR 70 ttiat will authorize the applicant to receive,
- possess, inspect, and store 800 fresh fuel assemblies for eventual use in the Nine tlile Point Nuclear Station.
The license would be effective until it can be superseded by t!iagara Mohawk's operating license for Unit 2 under 10 CFR 50.
lhe fuel asseoblies contain uranium dioxide (UO
) pellets that have a rIaxi mum uraniupI-235 enrichment of 3.05 percent by weight a3d are encapsulated in zi rcaloy tubing.
Issuance of the license would result in receipt, possession, inspection, and storage of the unirradiated fuel at Nine IIile Point.
The transport of new fuel to t!ine tiile Point will be the responsibility of the fuel fabricator.
However, the license would authorize the applicant to transport or deliver to a carrier for transport the assemblies in approved packages if this should become necessary (e.g., to return fuel to the manufacturer).
In addition, authorization to use sealed sources in monitoring devices, which is currently authorized by an existing license, would also be incorporated into the Unit 2 license.
t!eed for the Proposed Action The applicant proposes to receive and store fresh fuel prior to issuance of the Par't 50 operating license in order to inspect the asseohlies and to finalize fuel preparation (e.g., add necessary hardware) needed to load the fuel into the reactor core vessel.
Actual core loading, however, will not be OFFICE)
SURNAME)
DATE) stage wil
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Alternatives to the Proposed Action and Their Environmental I
acts Alternatives to the proposed action include complete denial of Niagara Mohawk's application.
Assuming the operating license will eventually be issued, denial of the storage only license now would merely postpone the new fuel receipt.
Such action, as well as any other alternative that can be imagined, would not present an environnantal advantage
- because, as discussed below, no environtn ntal impacts are expected to result from the proposed action.
Environmental Impacts of the Proposed Action A Final Environoental Statement (FES) related to the full-scale operation of the Nin~ Mile Point Nuclear Station has already been prepared and issued by the NRC Based on the evaluation in this statement, the environm ntal irryacts of plant operation, subject to proposed conditions for environoental protection, are expected to be small.
Plant operations will eventually include the storage and handling of irradiated fuel which is significantly more hazardous than unirradiated fuel.
Therefore, the environoental impact from handling unirradi-ated fuel is expected to be very minor.
Once at Nine Mile Point, the new fuel will be received in the fuel receiving area and stored tenporarily prior to being removed from the shipping containers.
The fuel may also be stored within its shipping container on the refueling floor or in its shipping crate in the fuel receiving area.
Smear surveys will be perforated on the transport vehicle and on the new fuel shipping crates.
The new fuel will then be removed from its shippping container, surveyed for external contamination, inspected, and transported to a storage location.
Only a snell amount, if any, of radioactive waste rIay be generated during this handling (e.g.,
smear papers or contaminated package naterial) and any waste that is produced will be properly stored onsite until it can be shipped to a licensed disposal facility.
The fuel will be stored in the llew Fuel Storage Vault or the Spent Fuel Storage Pool.
Administrative controls conhined with the design of these storage locations will ensure acceptable protection of the fuel assetTblies from excessive physical damage under normal or abnormal condi tions.
In the event the applicant ttmst return assenhlies to the fuel manufacturer, all packaging and transport of fuel will be in accordance with 10 CFR 71.
The package will rreet HRC approval requireoents for normal conditions of transport and hypothetical accident conditions.
No significant external radiation hazards are associated with the unirradiated assemblies because the radiation level from the fuel is low (the exposure rate at 1 foot from the surface is normally less than 1 mr/hr) and because the shipping packages nast neet the external radiation standards in 10 CFR 71.
Therefore, any shipment of unirradi-ated fuel by the applicant is expected to have an insignificant environoental impact.
OFFICE)
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DATEP
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cl ear"Regul ak y"Gemmi ssio tiop of Nine i le.l'.p.)II/..N.u ohawk Power C rporation,"
~.-"Final
"Envi ear Station REG-1085, Ha
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3w gay 4 585 In the unlikely event that an assettbly (either within or outside its shipping container) is dropped during transfer, the fuel cladding is not expected to rupture.
Even if the fuel rod cladding were breached and the pellets were
- released, an insignificant environmntal impact would result.
The fuel pellets are cotIposed of a ceramic UO that has been pelletized and sintered to a very high density.
In this fork, the generation of-UO aerosol is unlikely except under conditions of deliberate grinding.
A)ditionally, UO is soluble only in acid solution so dissolution and release to the envi ronknt is extremely unlikely.
All fuel handling activities will be in accordance with approved procedures to assure nuclear criticality and radiation safety.
Fuel assemblies are handled individually, not disassembled into single fuel rods, and are stored as full asses@lies.
No single asserrbly can be made critical independent of the degree of water moderation and/or reflection.
Safety of the stored assettblies is assured by several engineered safeguards (see the Safety Evaluation Report supporting this license).
Moreover, the fuel assenblies are normally stored dry and under these conditions, cannot be made critical
(< 5.0 percent U-235 enrichment) independent of the number of asserrblies and spacing between them. Therefore, the proposed fuel handling and storage activities are critically safe and no environrrental i~acts from an accidental criticality are expected.
Conclusion Based upon the information presented above, the envi ronaental impacts associated with new fuel storage at N!ine Mile Point Nuclear Station are expected to be insignificant.
Essentially no effluents will be released and acceptable controls will be iIIylenented to prevent a radiological accident.
Therefore, in accordance with 10 CFR 51.31, a Finding of No Significant Impact is considered appropriate for this action.
QBglgQ) gfgged gy Mom Horn Or 8)~y S j g10d, BVe, g.
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Merri Horn Uranium Process Licensing Section Uranium Fuel Licensing Branch Oivisi on of Fuel Cycle and Material Safety,NMSS Approved by:~l..
- roe, ect on ea er OFFICK)
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DATE$
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