IR 05000333/1979005
| ML19269E938 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/20/1979 |
| From: | Kotton J, Stohr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19269E934 | List: |
| References | |
| 50-333-79-05, 50-333-79-5, NUDOCS 7906290842 | |
| Download: ML19269E938 (4) | |
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U.S. NUCLEAR REGULATORY CCMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-333/79-05 Docket No.
50-333 C
License No. DPR-59 Priority
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Category Licensee:
Power Authority of the State of New York 10 Columbus Circle New York, New York 10019 Facility Name:
James A. FitzPatrick Nuclear Power Plant Inspection at:
Scriba, New York Inspection conducted:
Marph 15,1979 Inspectors:
[df dl Y' 24 - 7 f J. J. Ko,ttan, Radiation Specialist date signed date signed
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date signed Approved by:
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J. P./ tohr, Chief, Environmental and Special
'date signed
/ Projects Section, FF&MS Branch Insoection Summary:
Inspection on March 15,1979 (Report No. 50-333/79-05)
Areas Inspected:
This report contains the results of an effluent sample split between the licensee and NRC:I during a previous inspection on September 27-29, 1978. The comparison of these results involved no onsite time.
Results: Within the area inspected, no items of noncompliance were observed.
2142 226 79062908f[ Q Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted E. Mulcahey, Radiation Protection and Radiochemistry Supervisor 2.
Confirmatory Measurements In a previous inspection conducted on September 27-29, 1978 Inspec-tion R]porc 50-333/78-20, a liquid effluent sample was split with the licensee and NRC:I. Analyses were performed by the licensee using his normal methods and procedures, and the NRC:I analyses were performed by the Department of Energy's Radiological and Environmental Services Laboratory (RESL). The comparison of the analyses results indicated that all of the measurements were in agreement or not comparable under the criteria used for comparing results (See Attachment 1).
The results of the comparisons are presented in Table I.
No items of noncompliance were identified.
3.
Exit Interview The inspector discussed the results of this inspection in a tele-phone conversation on March 15, 1979 with the licensee representa-tive denoted in Paragraph 1.
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TABLE 1 FITZPATRICK VERIFICATION TEST RESULTS SAMPLE IS0 TOPE NRC VALUE LICENSEE VALUE COMPARISON RESULTS IN MICR0 CURIES PER MILLILITER FDST Sr-89 (312) E-8 (1.1810.67) E-8 No Comparison 1035 hrs Sr-90 (514) E-9
< 7.81 E-9 No Comparison 9/28/78 Gross Beta (2.710.1 ) E-5 (2.710.48) E-5 Agreement Gross Alpha (312) E-9
< l.27 E-9 No Comparison H-3 (2.9410.02) E-4 (3.2410.32) E-4 Agreement N
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N N
N CD
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Attachment 1 Criteria for Comparing Analytical Measurements This attachment provides criteria for comparing results of capability tests and verification measurements.
The criteria are based on an empirical relationship which combines prior experience and the accuracy needs of this program.
In these criteria, the judgement limits are variable in relation to the comparison of the NRC Reference Laboratory's value to its associated uncertainty.
As that ratio, referred to in this program a,s " Resolution",
increases the acceptability of a licensee's measurement should be more selective.
Conversely, poorer agreement must be considered acceptable as the resolution decreases.
LICENSEE VALUE RATIO = NRC' REFERENCE VALUE Possible Possible Resolution Agreement Agreement A Agreement B
<3 0.4 - 2.5 0.3 - 3.0 No Comparison 4-7 0.5 - 2.0 0.4 - 2.5 0.3 - 3.0 8 - 15 0.6 - 1.66 0.5 - 2.0 0.4 - 2.5 16 - 50 0.75 - 1.33 0.6 - 1.66 0.5 - 2.0 51 - 200 0.80 - 1.25 0.75 - 1.33 0.6 - 1.66
>200 0.85 - 1.18 0.80 - 1.25 0.75 - 1.33
"A" criteria are applied to the following analyses:
Gamma Spectrometry where principal gamma energy used for identification is greater than 250 Kev.
Tritium analyses of liquid samples.
Iodine on absorbers
"B" criteria are applied to the following analyses:
Gamma Spectrometry where principal gamma energy used for identification is less than 250 Kev.
89Sr and 90Sr Determinations.
Gross Beta where samples are counted on the same date using the same reference nuclide.
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UNITED STATES
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c'g NUCLEAR REGULATORY COMMISSION j
WASHINGTON, D. C. 20555 gg
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Docket Nos. 50-338/339 MAY 2 31979 Mr. W. Senior Vice President - Power Operations Virginia Electric & Power Company P. O. Box 26666 Richmond, Virginia 23261
Dear Mr. Proffitt:
' SUBJECT: RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS FOR NORTH ANNA POWER STATION, UNIT NOS. 1 AND 2
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In a letter, dated March 6, 1979, you submitted proposed Radiological Effluent Technical Specifications for an amendment to the license for North Anna, Unit No.1, and the intended use for Unit No. 2.
On March 28, 1979, we requested that you submit a Process Control Program (PCP) for solidification and an Offsite Ocse Calculation Manual (0DCM) for review.
On April 11, 1979, you responded in a letter indicating that you were evaluating your Ion Exchange System to justify shipments of wet dewatered resin without solidification, thereby demonstrating that a PCP will not be needed.
It is our position that wet radioactive wastes (e.g., filter sludges, spent resin, evaporator bottoms, boric acid solutions, and sodium sulfate solutions) shall be solidified, and that a PCP shall be used to verify solidification. NRC-IE Inspection Report 50-338/78-28 indicates that the waste evaporator at Unit No. 1 is not being used and we are informed that a vendor is processing evaporator feed through demineralizers.
Therefore, we require that you submit a PCP for the installed solid radwaste system and/or provide verification of the existence of a valid contract for solidification to be performed by a contractor, in accordance with a PCP submitted for our review.
In the April ll,1979 letter, you indicated that the information that we need in the ODCM is contained in a plant " manual" retained at the station.
While the " manual" may have the type of information we have requested, such station manuals usually contain greater detail than we need, as well as extraneous information, and do not always contain all of the information we have requested. We need a document that is prepared specifically for the Technical Specifications following the guidance that has been provided to you.
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Mr. W. W$
Therefore, we require that you submit the Solid Waste Process Control Program and the ODCM not later than July 1,1979, so that we may complete our review in a timely manner.
Sincerely, I.Tief
arr Light Water Reactors Branch No. 3 Division of Project Management cc: See next page
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Mr. W. L. Prof fitt-3-MAY 2 31979 cc:
Mrs. James C. Arnold John J. Rur:cr, Esq.
P. O. Box 3951 Pepper, Hamilton & Scheetz Charlottesville, Virginia 22903 123 South Broad St reet Philadelphia, Pennsyi.ania 19109
' Pr. Anthony Gambaradella
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Of fice of the Attorney General Cl arence T. Ki pps, Jr., Esq.
11 South 12th Street - Room 308 UOO Pennsyl vania Avenue,. ft.W.
Richmond, Virginia 23219 Washington, D. C.
20006 Carroll J. Savage, Esq.
Richard M. Foster, Esq.
1700 Pennsylvania Avenue, t;. W.
211 Stribling Avenue Washington, D. C.
20006 Charlottesville, Virginia 22903 Mr. James C. Dunstan Michael W. Maupin, Esq.
State Corporation Couaission Hunton, Williams, Gay & Gibson Cocmonwealth of Vi rginia P. O. Box 1535 Blandon Building Richmond, Vi rginia 23212 Richmond, Vi rginia 23209 Mrs. June Allen 412 Owens Drive
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Huntsville, Alabama 35801 Mr. James Torson Alan S. Rosenthal, Esq.
501 Leroy Atomic Safety and Licensing Socorro, New Mexico 87801 Appeal Board U.S. Nucleai' Regulatory Commission Mrs. Margaret Dietrich Washington, D. C.
20555 Route 2, Box 568 Gordonsville, Vi rginia 22942 Michael C. Fa rrar, Esq.
Atomic Safety and Licensing William H. Rodgers, Jr., Esq.
Appeal Board Georgetown University Law Center U.S. Nuclear Regulatory Commission 600 New Jersey Avenue, N.W.
Washington, D. C.
20555 Washington, D. C.
20001 Dr. John H. Buck Mr. Peter S. Hepp Atomic Safety and Licensing Executive Vice President Appeal Board Sun Shipping & Dry Dock Company U.S. Nuclear Regulatory Coanission P. O. Box 540 Washington, D. C.
20555 Chester, Pennsylvania 19013 Mr. R. B. Briggs Atomic Safety and Licensing Associate Director Board Panel 110 Evans Lane U.S. Nuclear Regulatory Commission Oak Ridge, Tennessee 37830 Washington, D. C.
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A Mr. W. G79 cc:
Mr. Michael S. Kidd U. S. Nuclear Regulatory Commission
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P. O. Box 128 Spotsivania, Virginia 22553 Dr. Paul W. Purdom Department of Civil Engineering Drexel University Philadelphia, Pennsylvania 19104 Dr. Lawrence R. Quarles Apartment No. 51 Kenda l-a t-Longwood Kennett Square, Pennsylvania 19348 Mr. Irwin B. Kroot Citizens Energy Forum P. O. Box 138 McLean, Virginia 22101
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James B. Dougherty, Esq.
Potomac Alliance P. O. Box 9306 Washington, D.C.
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