ML20205A551
| ML20205A551 | |
| Person / Time | |
|---|---|
| Site: | 07003014 |
| Issue date: | 04/16/1985 |
| From: | Crow W, Kodali K NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20205A485 | List: |
| References | |
| NUDOCS 8504250545 | |
| Download: ML20205A551 (12) | |
Text
9 L e DOCKET N0.:
70-3014 APPLICANT:
Northeast Nuclear Energy Company (NU)
Connecticut Light & Power Company Western Massachusetts Electric Company New England Power Company United Illuminating Company Public Service Company of New Hampshire Central Vermont Public Service Corporation Montaup Electric Company City of Burlington, Vermont, Electric Light Department Chicopee Municipal Lighting Plant Massachusetts Municipal Wholesale Electric Company Vermont Electric Generation and Transmission Cooperative, Inc.
Central Maine Power Company Village of Lyndonville Electric Department Connecticut Municipal Electric Energy Cooperative Fitchburg Gas and Electric Light Company FACILITY:
Millstone Nuclear Power Station (MNPP), Unit No. 3
SUBJECT:
Safety Evaluation Report - Review of License Application-dated January 28, 1985, and its supplement dated March 20, 1985, for a Material License.
I.
Introduction A.
General By application dated January 28, 1985 and its supplement dated March 20, 1985, Northeast Nuclear Energy Company (NU), on its own behalf and as agent for the other applicants listed above, requested authorization to receive, possess, inspect, and store enriched uranium fuel assemblies and other radioactive materials in the form of Californium Neutron Sources, U-235 Flux Mapping Detectors, an Am-Be Boronometer Source, U-235 Post Accident Monitoring Detectors, and Np-237 Irradiation Surveillance Capsules.
The materials license was requested to allow early receipt of the fuel for the purpose of inspection and preparation of the fuel for reactor loading.
The license will automatically
[
terminate upon issuance of the Part 50 operating license.
B.
Fuel Assembly Design Westinghouse Electric Corporation will supply the finished fuel assemblies.
Each fuel assembly contains 264 fuel rods (Zircaloy tubes with UO2 pellets),
24 guide thimble tubes, and 1 instrumentation thimble tube.
The fuel rods, guide thimble tubes, and instrumentation thimble tube are arranged in a 17 x 17 array and are supported by fuel grids which maintain the lateral spacing i
8504250545 850416 PDR ADOCK 07003014 C
PDR L
2 between rods.
Table 1 presents general fuel assembly parameters that describe the fuel which will eventually be used in the Millstone Nuclear Power Station (MNPP), Unit No. 3.
Table 1 MILLSTONE NUCLEAR POWER STATION, UNIT N0. 3 General Fuel Data Fuel Assembly Data Inches Overall Length 160.0 Nominal Active Fuel Length 144.0 Fuel Rod Pitch 0.496 Rod Array 17 x 17 Rods Per Assembly 264 Fuel Rod Data Fuel Pellet Material U02 Outside Diameter 0.374 Cladding Thickness 0.0225 Cladding Inside Diameter 0.329 Fuel Pellet Immersion Density (% theoretical) 95.0 Fuel Pellet Diameter 0.3225 C.
Location Description The MNPP, Unit 3, is located on a site in the town of Waterford, New London County, Connecticut, on the north shore of Long Island Sound. Already located on the site are two other nuclear units, Millstone 1 and Millstone 2.
Millstone 1 is a BWR supplied by the General Electric Company with a rated thermal power level of 2,011 MW.
Millstone 2 is a two-loop PWR supplied by Combustion Engineering, Inc. rated at a thermal power level of 2,700 MW. Millstone 3 is also a PWR.
However, it is a Westinghouse supplied 4-loop nuclear steam supply system.
The construction permit (CPPR-113) for MNPP, Unit 3, was issued by the Atomic Energy Commission on August 9, 1974.
II.
AUTHORIZED ACTIVITIES A.
Enriched Uranium Fuel Assemblies The. license will authorize the receipt, possession, inspection, and storage of 203 finished fuel assemblies with a maximum enrichment of a 3.45 w/o in U-235.
Fuel assemblies will be stored in their shipping containers and the storage racks in the spent fuel pool in the Fuel Building.
The applicant also requests authorization 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.
3 B.
Californium Neutron Sources The license will authorize the. receipt, possession, and storage of two (2)
Californium (Cf) sources each containing approximately 0.000345 grams of Cf-252 which will be used as primary startup sources for the reactor.
In addition, the license will authorize attaching the sources to an insert and storing them in the spent fuel pool.
The maximum count rate for each source will be 8 x 108 neutrons /second or approximately 0.2 curies.
The applicant requests that the license be for a nominal 0.5 curies of Cf-252.
C.
Flux Mapping Detectors The license will authorize the receipt, possession, and storage of eight (8) flux mapping detectors.
Each detector contains 0.0039 grams of U-235.
D.
Boronometer Source The license will authorize the receipt, possession, and storage of one (1)
Am-Be source containing a maximum of one curie.
E.
Post-Accident Monitoring Detectors The license will authorize the receipt, possession, and storage of three (3) post-accident monitoring Gammametrics detectors each containing approximately 8 grams of U-235 enriched to 93%.
F.
Irradiation Surveillance Capsules The license will authorize the receipt, possession, and storage of six (6) irradiation surveillance capsules, containing a total of 25.0 x 10 3 raicro-curies (approximately 4.0 x 10 3 microcuries/ capsule) of U-238 and 75.0 microcuries (approximately 12.0 microcuries/ capsule) of Np-237.
III.
SCOPE OF REVIEW The staff safety review of the NU request for a material license included evaluation of the Millstone Nuclear Power Station organization, administration, nuclear criticality safety, radiation protection, and fire protection program.
During the course of the review, discussions were held with the NRR Project Manager, the Senior Resident Inspector, Region I, and NU staff members.
The evaluation of the " Millstone Station Physical Security Plan" was made by the Physical Security Licensing Branch, Division of Safeguards, Office of Nuclear Material Safety and Safeguards.
- s 4
IV.
POSSESSION LIMITS
' Conditions 6, 7, an'd 8 of the license will specify the type, form, and quantity of material the licensee may possess under this license and shall read as follows:
6.
Material 7.
Form 8.
Quantity A.
Uranium enriched A.
In unirradiated A.
3185 kg of.U-235
~in the U-235 isotope reactor fuel in uranium enriched assemblies to no more than 3.45 w/o in U-235 B.
Californium 252 B.
Primary startup-B.
0.6 curies of Cf-252 source C.
Uranium enriched C.
Flux mapping C.
45 mg of U-235 in
-in the U-235 detectors uranium enriched to isotope greater than 20 w/o in U-235 D.
Am-Be-D.
Double encapsulated D.
1 curie Boronometer source
. E.
Uranium enriched E.
Post-accident E.
25 g of U-235 in the U-235 monitoring enriched to 93 w/o
' isotope detectors in U-235 F.
U-238, Np-237-F.
Irradiation F.
25 x 10 3 microcuries surveillance U-238 plus 75 micro-capsules curies-Np-237 V.
ORGANIZATION
~
- A. - Nuclear Criticality Safety and Radiation Protection Responsibilities l
1.
Unit Superintendent l
.The MNPP Unit ~3 Superintendent coordinates and manages all plant activities L
-including: maintenance; operations; engineering services; administration of-
. established corporate policies, programs, and procedures and is Chairman of the' Plant Operations Review Committee (PORC).
The PORC reviews and recommends approval of all procedures related to operations within MNPP, Unit 3.
- 2.
Reactor Engineer The Reactor Engineer is responsible for coordinating the performance.of duties relating to fuel inventory and control, reactivity and other nuclear calculations and control, routine parametric evaluations, and:is also a member of PORC.
The Reactor-Engineer is responsible for overseeing and maintaining the special
-nuclear material accountabilit_y program.
_~
5 3.
Operations Supervisor The Operations Supervisor supervises the operation of generating and associated
. equipment of the plant in compliance with applicable federal, state, and local regulations and within corporate policies.
4.
Shift Supervisors The Shift Supervisors coordinate and supervise the operation of the plant during assigned rotating shifts in compliance with applicable federal, state, and locc1 laws, regulations, and licenses. The Shift Supervisor ' assumes initial responsibility during a site emergency.
5.
Radiation Protection Supervisor The Radiation Protection Supervisor is responsible for radiation protection activities including detecting and controlling radiation contamination. The responsibilities include monitoring, approving, and documenting the receipt, storage, use and/or shipment of radioactive materials for conformance to applicable regulations.
B.
Minimum Qualifications The qualifications of the aforementioned safety-related personnel have been reviewed and the staff finds they meet the minimum qualifications specified in Regulatory Guide 1.8, " Personnel Selection and Training" and/or ANSI /N18.1-1971,
" Selection and Training of Nuclear Power Plant Personnel." The NRC staff recommends License Conditions 11, 12, 13, 14, and 15 to highlight the minimum qualifications for the positions of Unit Superintendent, Reactor Engineer, Operations Supervisor, Shift Supervisor, and Radiation Protection Supervisor.
Condition 11. The minimum technical qualifications for the Unit Superin-tendent shall be in accordance with Section 4.2.1, " Plant Manager," ANSI /N18.1-1971.
Condition 12. The minimum qualifications for the Reactor Engineer shall be in accordance with Section 4.4.1, " Reactor Engineering," ANSI /N18.1-1971.
Condition 13. The minimum qualifications for Operations Supervisor shall be in accordance with Section 4.3.1, " Supervisors Requiring AEC Licenses," ANSI /N18.1-1971.
Condition 14. The minimum qualifications for Shift Supervisor shall be in accordance with Section 4.3.2., " Supervisors Not Requiring AEC Licenses," ANSI /N18.1-1971.
Condition 15. The minimum qualifications for Radiation Protection Super-visor shall be in accordance with the requirements for
" Radiation Protection Manager", Regulatory Guide 1.8, September 1975.
6 C.
Training Training is conducted to ensure that all fuel handling personnel are familiar with the designed features, engineering safeguards, and fuel handling procedures.
The Reactor _ Engineer is responsible for developing and implementing the nuclear criticality safety training program.
Radiation Control personnel, in addition to receiving fuel handling training, will receive Health Physics training.
Because the training requirements were not clearly defined in the application submitted by NU, the staff recommends that Condition 16 be added to highlight the required training program.
Condition 16.
The following training shall be conducted prior to receipt of fuel onsite:
a.
All radiation safety personnel shall be trained in radiation safety and NU radiation protection procedures related to fuel assembly bandling.
b.
All operations personnel involved in fuel handling shall receive training in proper fuel handling proce-dures, including health and safety aspects of the activities.
The staff has concluded that, based on these added conditions and the applicant's radiation safety and fuel handling training programs, the licensee can responsi-bly carry out the activities for which a license is requested.
D.
Administrative Procedures Administrative procedures for the control and handling of nuclear fuel are reviewed and approved by the Plant Operations Review Committee (PORC).
PORC membership is per Millstone Unit 3 Draft Technical Specification 6.5.1.
The responsibilities and qualifications of PORC members are described in Chapter 13 of the Millstone Unit 3 FSAR.
Final approval of these procedures, based on the recommendations of the PORC, is by the Millstone Unit 3 Superintendent.
VI.
Nuclear Criticality Safety The applicant requests authorization to store fuel assemblies in their shipping containers in the new fuel unloading area and in the spent fuel storage pool of the Fuel Building.
A.
Fuel Handling In order to be sure that the fuel handling equipment is ready to safely handle the fuel assemblies, the staff recommends that the following license. condition be added:
7 Condition 17.
All preoperational testing of fuel handling equipment, related to activities authorized by this license, shall be completed and these results shall be reviewed and approved by NU engineering before receipt of fuel onsite.
This includes the testing of the following:
a.
New Fuel Receiving Crane b.
New Fuel Handling Crane c.
Spent Fuel Bridge and Hoist d.
New Fuel Elevator e.
Spent Fuel Assembly Handling Tool f.
New Fuel Assembly Handling Tool g.
Spent Fuel Storage Racks in the spent fuel pool.
NU's application states that no more than two assemblies will be out of their shipping containers or storage racks at a given time.
Calculations have indicated that two assemblies could be made critical at optimum conditions of water moderation and reflection; however, one assembly, separated from another assembly by 12 inches of spacing cannot be made critical under any conditions.
Therefore, the staff recommends the following license conditions limiting the number of fuel assemblies out of storage and the minimum distance from each other and from all other fuel:
Condition 18.
No more than two fuel assemblies shall be out of approved shipping containers or fuel assembly storage racks at any given time.
Condition 19.
The minimum edge-to-edge distance between the two fuel assemblies and the shipping container array and storage rack arrays shall be 12 inches.
B.
Shipping Containers The fresh fuel assemblies will be temporarily stored in shipping containers in the new fuel receiving area of the Fuel Building.
The shipping containers are authorized for use in accordance with Certificate of Compliance No. 5450, Revision 19.
The Certificate of Compliance authorizes the shipment of as many as 60 containers filled with unirradiated fuel assemblies in a single Class III shipment independent of stacking or the degree of water moderation and reflection.
NU requests authorization to store up to 12 shipping containers together in an array stacked two high with a minimum of 10 feet separation between shipping container arrays.
The NRC staff finds that there is no nuclear criticality safety hazard when 12 containers are stored in a single array with at least 10 feet separation (edge-to-edge) between arrays.
C.
Spent Fuel Storage Facility The licensee rakes no mention of a new storage vault for fuel assemblies.
Therefore, all fuel assemblies, stored out of the shipping containers, shall
8 be in the spent fuel storage pool storage racks.
The fuel assemblies in the racks in the spent fuel storage pool are spaced on 10.35 inch centers.
The storage cells are 8.75 inches square and are made of 0.06 inch-thick stainless steel.
Subcriticality of the fuel assembly array is maintained by the presence of neutron poison plates (Boroflex) encapsulated on all four sides of each cell.
The staff has reviewed the NU quality assurance program to ensure that the neutron poison meets design specifications and is encapsulated securely to the storage racks.
The quality assurance program was found to be adequate.
NU conducted a criticality safety analysis for these storage rack arrays based on the following conditions:
the fuel assembly contains the highest enrichment, there are no non-contained burnable poisons present, the array is infinite in the lateral extent, credit is taken for neutron absorption in structural materials, and full water density.
Based on these conditions and using 218
_ group cross section sets in KEN 0 IV, NU determined that fresh fuel stored in the spent fuel storage pool would have a maximum k-eff of less than 0.95.
An independent nuclear criticality safety analysis by the staff indicates the k-eff of an infinite array of fuel assemblies at an enrichment of 3.45 w/o U-235 is 0.88 at full water density (optimum moderation).
Therefore, the array is safe.
D.
Exemption from Criticality Alarm Requirements The licensee has requested, pursuant to 10 CFR 70.24(d), an exemption from the provisions of 10 CFR 70.24.
Because of the inherent features associated with the storage and inspection of unirradiated fuel containing uranium enriched to less than 5% in the U-235 isotope when no fuel processing activities are to be performed and the inherent features in handling limited quantities of other radioactive materials, the staff hereby determines that granting such an exemption will not endanger life or property.
This exemption is authorized pursuant to 10 CFR 70.14.
It is recommended that the exemption be identified as Conditon 20.
Condition 20.
The licensee is hereby exempted from the provisions of 10 CFR 70.24 insofar as this section applies to materials held under this license.
VII.
RADIATION SAFETY Since all radioactive material, including fresh fuel assemblies, are sealed sources, the principal exposure pathway to an individual is via external radiation.
For a low-enriched uranium fuel bundle (< 4% U-235 enrichment),
the exposure rate at 1 foot from the surface is normally less than 1 mr/hr; therefore, it is estimated that the exposure level to workers from these sources would be less than 25% of the maximum permissible exposure.specified in 10 CFR 20.
All other special nuclear material requested by the licensee will also present no threat to plant personnel or to the environment because of the small quantities of radioactive material involved.
9.
At MNPP Unit 3, all persons subject to occupational radiation exposures will be
-issued thermoluminescent dosimeters (TLD's) and will be required to wear such
.TLD's at.all times while within any radiation control area.
The TLD's will be
. evaluated at monthly-intervals:by Northeast Utilities Service Company Dosimetry
. Laboratory or more frequently at the discretion 'of health physics personnel.
In addition, TLD's'will be immediately processed whenever it appears that an overexposure has occurred.
Storage of other radioactive. materials (other.than non-irradiated fuel) will be
-in,a locked Hi-Rad caged area within the Unit 3 Fuel Building and/or designated Special Nuclear Material. Storage Area of Millstone licensed units (i.e. Millstones 1/2). Access to unauthorized personnel is controlled by the presence of a guard as described in the'SNM Security Plan.
During the storage period, materials in the Hi-Rad caged area will be surveyed by health physics personnel on a weekly basis for boundary radiation levels and at a period not to exceed 6 months for swipe testing.
The Reactor Engineer is responsible for control of material within the Hi-Rad caged area.
Annex A, " License Condition for Leak Testing Sealed Byproduct Material. Sources",
has been adopted as a Branch Technical Position and will be incorporated as license Condition 21.
Accordingly, Condition 21 shall read as follows:
Condition 21.
The licensee shall comply with provisions of Annex A,
" License Condition for Leak Testing Sealed Byproduct Material Sources."
Because of the low-radiation exposure levels associated with the requested materials and activities and the licensee's radiation protection procedures, the~
. staff.has concluded that the requested operation can be carried out with
. adequate protection of the operating personnel.
VIII.
ENVIRONMENTAL PROTECTION The NRC has prepared an Environmental Assessment related to the proposed-10 CFR 70 Fuel Storage License for MNPP, Unit 3.
Based on this assessment, a-Finding of No Significant Inpact has been issued and approved pursuant to 10 CFR 51.
This finding was published in the Federal Register on April 10, 1985.
IX.
FIRE SAFETY The materials used in the fuel storage area are steel and concrete with the exception of cable insulation material and wooden scaffolding..The cable insulation' material has incorporated fire retardant characteristics into its design that make it difficult to ignite when exposed to open flame and slow
. burning once ignited.
The wooden scaffolding is treated with fire retardant
' chemicals that limit fire spreading potential.
In addition, procedures such
.as housekeeping practices and control of combustible materials will be strictly enforced.
The fire protection system within MNPP, Unit 3, storage areas consists
10 of ample water supplies and hoses (manual water hose stations), portable fire extinguishers, smoke detectors, and alarms.
The staff has determined that the fire protection measures taken by NU are adequate for the protection of the health and safety of the workers and_the public.
X.
PHYSICAL PROTECTION The Division of Safeguards, NMSS, has reviewed NU'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 22.
Condition 22.
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 Physical Security Plan consists of Revision 1 to the Plan for Receipt of.Special Nuclear Material of Low Strategic Significance for Millstone Nuclear Power Station, Unit No. 3, dated March 1985.
The Physical Security Plan shall be withheld from public disclosure pursuant to 10 CFR 2.790(d).
XI. CONCLUSIONS After reviewing the application and its supplement, the staff finds that:
a.
The applicant meets the requirements of the Atomic Energy Act, as amended, and of the regulations of the Commission, 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.
XII.
RECOMMENDATIONS The staff recommends approval of the application and its supplement subject to the following conditions which the staff finds are appropriate to protect health or to minimize danger to life or property.
Condition 11.
The minimum technical qualifications for the Unit Superin-tendent shall be in accordance with Section 4.2.1, " Plant l
Manager," ANSI /N18.1-1971.
Condition 12.
The minimum qualifications for the Reactor Engineer shall be in accordance with Section 4.4.1, " Reactor Engineering," ANSI /N18.1-1971.
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~
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11 Condition 13.-
The minimum qualifications for Operations Supervisor shall be in accordance with Section 4.3.1, " Supervisors Requiring AEC Licenses," ANSI /N18.1-1971.
Condition 14.
The minimum qualifications for Shift Supervisor shall be in accordance with Section 4.3.2., " Supervisors Not Requiring AEC Licenses," ANSI /N18.1-1971.
Condition 15.
The minimum qualifications for Radiation Protection Super-visor shall be in accordance with the' requirements for
" Radiation Protection Manager," Regulatory Guide 1.8, September 1975.
Condition 16.
The following training shall be conducted prior to receipt of fuel onsite:
~
~
a.
All radiation safety personnel shall be trained in radiation safety and NU radiation protection procedures related to fuel assembly handling.
b.
All operations personnel involved in. fuel handling shall receive training in proper fuel handling proce-dures, including health and safety aspects of the activities.
f-Condition 17.
All preoperational testing of fuel handling equipment, related to activities authorized by this license,'shall be completed.and these results_shall be reviewed and approved by NU engineering before receipt of fuel onsite.
This includes the testing of the'following:
a.
New Fuel Receiving Crane b.
New Fuel Handling Crane c.
Spent Fuel Bridge and Hoist d.
New Fuel Elevator e.
Spent Fuel-Assembly Handling Tool f.
New Fuel Assembly Handling Tool g.
Spent Fuel Storage Racks in the spent fuel pool Condition 18.
No more than two fuel assemblies shall be out of approved shipping containers or fuel assembly storage racks at any given time.
Condition 19.
The minimum edge-to-edge distance between the two fuel assemblies and the shipping container array and storage I
rack arrays shall be 12 inches.
Condition 20.
The licensee is hereby exempted from the provisions of 10 CFR 70.24 insofar as this section applies to materials held under this license.
u
12 Conditon 21.
The licensee shall comply with provisions of Annex A,
" License Condition for Leak Testing Sealed Byproduct Material Sources."
Condition 22.
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 Physical Security Plan consists of Revision 1 to the Plan for Receipt of Special Nuclear Material of Low Strategic Significance for Millstone Nuclear Power Station, Unit No. 3, dated March 1985.
The Physical Security Plan shall be withheld from public disclosure pursuant to 10 CFR 2.790(d).
4 Original silm@h Shore Kcda Kishore K. Kodali Uranium Process Licensing Section Uranium Fuel Licensing Branch Division of Fuel Cycle and Origina1 Signed By:
Material Safety, NMSS L T. Crow Approved by:
W. T. Crow, Section Leader y
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