ML20202C544
| ML20202C544 | |
| Person / Time | |
|---|---|
| Site: | 07003008 |
| Issue date: | 06/06/1986 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Davies J, Jennifer Davis NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML19292F560 | List: |
| References | |
| 27101, 2NRC-6-062, 2NRC-6-62, NUDOCS 8607110305 | |
| Download: ML20202C544 (4) | |
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rei copy (41e) 643 5200 suppingpart, pa 15o77 June 6, l'9h6 C EC EF.TD United States Nuclear Regulatory Commission Wasbington, DC 20555 ATTENTION:
Mr. John G. Davies, Director Nuclear Material Safety and Safeguards sN occWG
SUBJECT:
Beaver Valley Power Stat' ion - Unit No. 2
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usW JM1g9%6)1 Docket No. 50-412 Special Nuclear Material License--SfN 1954 5
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REFERENCE:
1.
2NRC-4-152 dated September 28, 1984 g ctERK 2.
2NRC-5-130 dated September 13, 1984 4
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2NRC-6-014 dated February 10, 1986 A
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2NRC-6-016 dated February 26, 1986 5.
Letter to J. J. Carey fr om W. T. Crow dated April 9,1986 Gentlemen:
Enclosed, please find, one (1) original plus six (6) copies of Revision 3 to the Beaver Valley Power Station - Unit No. 2 " Application for Special Nuclear Material License" submitted under the above references.
This revision (Attachment 1) updates Section 3.3 "Other Material Requiring NRC License", to include addi tional monitor check sources and requests an increase in the maximum anount that the licensee may possess at any one time as shown under Item 8 of SNM-1954 (Attachment 2) and page 3 of the Safety Evaluation Report (Attachment 3).
Duquesne Light Company has reviewed the Special Nuclear Material License and has the following conments:
Please include as item H to the license "approximately 1 curie of Sodium 24".
This isotope will be used as a radioactive tracer during power ascension testing for steam generator moisture carryover determination.
l Power Station Operations Quality Control Inspector have been reviewed and found acceptable by the NRC, letter fran Steven A.
Vargas to J.
J.
Carey dated August 12, 1982.
Therefore, please revise condition 12 to state that "The minimum technical qualifications for the Operations Quali ty Control Inspector shall be in accordance with ANSI 45.2.6 (1978) as referenced by Regulatory Guide 1.58 (1980)"
Condition 14 should be revised to reflect a change to the position ti tl e.
The new title is Manager, Radiological Control.
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United States Nuclear Regulatory Commission Mr. John. G. Davies Special Nuclaer Material License - SNM 1954 Page 2 Also enclosed (Attachment 4) is a revision to the DLC plan to control the BVPS-2 Fuel Building and adjacent area for temporary storage of fuel from date of receipt until operating license issuance.
DLC hereby requests authority to establish a temporary Controlled Access Area (CAA) at its BVPS-2 property, under the provisions of 10CFR76.67(f).
This temporary CAA will be established in the BVPS-2 Fuel Building and adjacent laydown area as shown on Attachment 4.
Please revise the Licensees address on the " Materials License" Item 2 and the Amendment to Indemnity Agreement No. B-73 Amendment No. 8" to P. 0 Box 4 Shippingport, PA 15077 Upon receipt of the revised Indemnity Agreement, all parties to the license will sign the agreement and return one original to the NRC.
If you should have any questions, please contact Thomas Zogimann at (412) 643-5200, extension 232.
DUQUESNE LIGHT COMPANY By A
J. J. Carey F
Vice President TJZ/ijr NR/SNM/1954 Attachment cc: Mr. P. Tam, Project Manager (w/a)
Mr. W. Troskoski, Sr. Resident Inspector (w/a)
Mr. L. Prividy NRC Resident Inspector (w/a)
INPO Records Center (w/a)
NRC Document Control Desk (w/a)
Mr. N. Ketzlach (NRC) (w/a))
Mr. G. Gunderson (NRC) (w/a
ATTACHMENT 1 Container in which sealed source is to be stored and model number The container is a shipping cask approximately 60" x 40" x 195" which weighs approximately 9 tons.
The model number is Model 2501, USA Dot SP5916 Type B or Model 2511 Type A.
3.3 The following infonnation is for the various detector calibration and check sources (sealed) and monitors used in the Digital Radiation Moni-toring System.
Upon receipt, this material will be stored in Storeroom No.
22 (non-exempt sources) and Warehouse "D"
(exempt sources) in accordance with ANSI N45.2.2.
Security and accountability pr actices consistent with NRC requirements have been established and are maintained in accordance with procedures specifically developed for this purpose.
The General Manager, Nuclear Services Unit has the overall responsiblity for implementation of the security and accountability practices and radi-ological control procedures.
Radiological control procedures have been established to prevent access to the check sources by unauthorized per-sonnel.
Additionally, only qualified radiological control personnel are authorized to utilize the check sources in a manner consistant wi th established practices to protect personnel from radiation exposure.
This material is being supplied by GA Technologies, Inc., and is shipped in D0T-approved containers.
Various area and process monitor detector calibration and check sources that are individually in exempt quantity (each less than approximately 10 microcurie Cs 137 or C1 36).
In addition to the 3
above:
One (1) area monitor (Type 4501) with 2 each 200uCi Cs 137 check 3
sources Two (2) area monitors (Type 4401) each with approximately 0.11 mg U234 and approximately 0.58 mg U 238 check sources One (1) Wide Range Gas Monitor (Monitor Type 5001 WRGM Detection) 3 with two (2) approximately 100 microcurie Cs 137 check sources Four (4) Liquid Monitors (Monitor Type 2301) each with approximately 100 microcurie Cs 137 check sources For calibrating the area monitor detectors:
Two (2) each approximately 10 millicurie Cs 137 sources 3
Two (2) each approximately 100 millicurie Cs 137 sources 14
For calibrating the process monitor detectors, the calibration kits will contain:
Two (2) each 0.4 microcurie Ba 133 sources and 10.1, 10.5 micro-curies Ba 133 Two (2) each approximately 110 microcurie and three (3) approxi-mately 10 microcurie Cs 137 sources One (1) adjacent-to-line monitor (type 3301) with check source 3
containing approximately 100 microcurie Cs 137 One (1) Steam Line Monitor with three check sources approximately 10uCi, 50uC1, 100uCi Cs 137) 3.4 The following information is for a radioactive tracer to be used during 3
power ascension testing. Approximately 1 curie of Na 24.
3.5 Each sealed source containing radioactive material either in excess of 3
100 microcuries of beta and/or gamma emitting inaterial or 5 microcuries of alpha emitting material shall be free of 0.005 microcuries of removable contamination.
This limit, based on T0CFR70.39(c) limits for plutonium, will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.
The detector, source rods, and calibration and check sources will be retained in their shipping crates (the crates will be resealed if requir-ed to be opened for receipt inspection).
Each of the detectors, source
- rods, and calibration and check sources shall be surveyed for contamination and/or tested for leakage upon receipt and prior to use or transfer to another user unless they have been leak-tested within six months prior to the date of use or transfer.
Records of results of the contamination surveys will be maintained for inspection.
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, 5 84' U.S. NUCLEAR REGULATORY COMMISSION MATERIALS LICENSE l
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 I, Parts 30,31,32,33,34,35,40 and 70, and in reliance on statements and representations y
heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, posrss, and transfer byproduct, p source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below;to y
deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This P
license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is E
subject to all applicable rules, regulations and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any E
conditions specified below.
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- E Duquesne Light Company l
I" Ohio Edison Company
- 3. Ucense number SfN-1954 The Cleveland Electric Illuminating Company The Toledo Edison Company F
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- 2. Robinson Plaza II Po h-4 p
Is Suite 210 Neg.qpen 9A
- 4. Expiration date March 31, 1991, or **
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PA Route 60 LPittsburgh, Pennsylvania 85071
- 5. Docket or
! 70-3008 Reference No.
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- 6. Hyproduct, source, and/or
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In unirradiated.
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200 uCi of Cf-252, p
maximum 100uCiperroo(
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Cs-137 D.
Various calibration D.
millicuries of h
and check sources Cs-137, maximum of N
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Ba-133 E.
Calibration source E.
Ba-133, maximum of 1 microcuries of 4
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microcurie per source i
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- Duquesne Light Company (DLC) is authorized to act as agent for the Ohio Edison Company, p!
the Cleveland Electric Illuminating Company, and the Toledo Edison Company, and has D
H exclusive responsibility and control over the physical construction, operation, and N
i maintenance of the facility.
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MATERIALS LICENSE SNM-1954 M
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Authorized Use:
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For receipt, possession, inspection, storage, and packaging of fuel assemblies and 5
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other special, source, and byproduct ma.terials for delivery to a carrier in l
q accordance with the statements, representatioas',-and conditions specified in DLC's application dated September,28, 1984, its revision datedsSeptember 13, 1985, and its s
supplements dated October.9, 1985, and February 10, 1986, except as specifically s
provided otherwise by this license.
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N 11. The minimum technical qualifications'forithe' Plant Manager shall be in accordance with
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- 12. The minimum technical'quali ations for' thel 0 erations Quality Control Inspector pl N
shall be in accordance with'Secti on 4 4.5,g"Ruality Assurance," ANSI /ANS-3.1-1981.
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- 13. The minimum technica1Cqualifications for the' Refueling' Supervisor shall be in accor-dance with Section 4.3.2',," Supervisors.Not RequiringiAEC Li. censes," ANSI N18.1-1971.
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4 414. The minimum technical qualif;ications for the Radiological' Operations Coordinator shall g
d be in accordance with the requirements for " Radiation Protection Manager," Regulatory s
1 Guide 1.8, September 1975.
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P) l 15. The following training shall be completed prior to receipt of fuel onsite:
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All radiation safety personnel involved in fuel handling operations shall be p
trained in radiation safety and DLC radiation protection procedures related to y
9 fuel assembly handling.
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All operations personnel involved in fuel handling operations shall receive 5
- q training in proper fuel handling procedures, including health and safety aspects l
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No more than two fuel assemblies shall be out of approved shipping containers or b
4 fuel assembly storage racks at any one time.
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The minimum edge-to-edge distance between the above two fuel assemblies, the l
h shipping container array, and the storage rack arrays shall be 12 inches.
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> 17. Fuel assemblies shall be stored in such a manner that water would drain freely from s
H the assemblies in the event of flooding and subsequent draining of the fuel storage W
area.
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y f 180 DLC is hereby exempted from the provisions of 10 CFR 70.24 insofar as this section l
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applies to materials held under this license.
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% 19. DLC shall comply with the provisions of Annex A, " License Condition for Leak Testing k
9 Sealed Byproduct Material Sources," dated November 1979.
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approved Physical Security Plan,' including changes' made pursuant to the authority of
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10 CFR 70.32(e). The approved' Physical Security Plan consists of " Plan to Control the BVPS-2 Fuel Building for-Temporary Storage of Fuel," transmitted by letter dated s
fl February 26, 1986.
The: Physical Security Plan shall be withheld from public disclosure p
j pursuant to 10 CFR 2.790(d).
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PJ ti FOR THE V.S. NUCLEAR REGULATORY COMMISSION R
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Date:
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Division of Fuel Cycle and F
Material Safety, NMSS 4
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APR 9 1986 C.
Primary Source Rods The license will authorize the receipt, possession, inspection, and use of two primary source rods, each containing Paladium-Californium 0xide as source material. A maximum of 100 uCi's is present in each sealed source.
D.
Calibration and Check Sources The license will authorize the receipt, possession, inspection, and use of the following calibration and check sources (sealed) and monitors:
a.
Various detector calibration and check sources, in exempt quantity (each with less than 10 microcuries Cs-137 or C1 36).
b.
One Wide Range Gas Monitor containing two sources, each with 100 q
microcuries Cs-137 neere d m y c.
For calibrating area monitor detectors:
- 1. Two, each withs10 millicuries Cs-137 yerm,,unny
?. Two, each with*100 millicuries Cs-137
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- 3. Four liquid monitors, each with{00 microcuries Cs-137 wm.nm m d.
For calibrating process monitor detectors:
1.
Two, each with 0.4 microcuries Ba-133,Mo eo.n ioS *CC hm e
2.
Two, each witho110 microcuries Cs-137 Aruc unacV T
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Three, each wi M 10 microcuries Cs-137 4.
One check source containingh100 microcuries Cs-137
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One Steam Line Monitor with three check sources containing
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less thany10, 50, and 100 microcuries Cs-137, respectively e.
One area monitor withv200 microcuries Cs-137 he.w f.
Two area monitors, each with 0.11 mg U-234 and 0.58 mg U-238 check sources h.
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III. SCOPE OF REVIEW The staff's safety review of the DLC request for a materials license included an evaluation of the BVPS organization, administration, nuclear criticality safety, radiation protection, and fire protection programs.
During the course of the review, discussions were held with the NRR Project Manager, the Senior Resident Inspector, and DLC staff members.
The evaluation of the "Duquesne Light Company, Beaver Valley Power Station Physical Security Plan" was made by the Power Reactor Safeguards Licensing Branch, Division of Safeguards, Office of Nuclear Material Safety and Sa fegua rds.
IV.
POSSESSION LIMITS Conditions 6, 7, and 8 of this license will specify the type, form, and quantity of material that DLC may possess under this license and shall read as follows:
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