IR 05000146/1986002
| ML20212K834 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 01/20/1987 |
| From: | Elsasser T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Heward R SAXTON NUCLEAR EXPERIMENTAL CORP. |
| References | |
| NUDOCS 8701290215 | |
| Download: ML20212K834 (3) | |
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JM 2 01987 Docket No. 50-146 Saxton Nuclear Experimental Corporation ATTN:
Mr. R. W. Heward, Jr.
President l' Upper Pond Road-Parsippany, New Jersey 07054 Gentlemen:
This refers to your letter dated September 24, 1986 to the NRC's Office of Nuclear Reactor Regulation (NRR), Attn: Document Control Desk, in which you provided a proposed mailing list for all Saxton related correspondence.
Based on recent dis-cussions with the NRR project manager for the Saxton reactor facility, we under-stand that your proposed mailing list for Saxton correspondence has been incorpor-ated by NRR into their service list for outgoing licensing related correspondence.
Also, with respect to inspection-related correspondence, we have added each of the addressees on your proposed mailing list, except the Saxton Community Library, to
our external document distribution service list for the Saxton reactor facility.
Please note that the Saxton Community Library is the designated local public docu-ment room (LPDR) for Saxton and, as such, already receives inspection-related, as
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well as other, docketed Saxton correspondenca.
Furthermore, any incoming corres-pondence, such as letters from yourself to the NRC, are routinely copied and sent to the PDR and LPDR, but are not copied by the NRC for service list distribution.
Accordingly, we are sending a copy of this letter to each addressee listed on the enclosed Saxton Reactor Facility Service List for NRC Region I outgoing correspon-dence.
In addition, we are providing each Service List addressee a copy of an NRC Region I letter dated December 12, 1986 and its enclosures regarding Inspection 50-146/86-02 at the Saxton reactor facility.
If any of the service list addressees wish to correct their mailing address, or if they do not want to receive similar inspection-related (or other) NRC correspondence, they should contact me by letter to this office or by telephone at (215) 337-5378.
Sincerely, Or:2in2121sacd Byt '
Thomas C. Elsasser, Chief Reactor Projects Section 3C Division of Reactor Projects
Enclosures:
As Stated 8701290215 870120 PDR ADOCK 05000146 9 14 PDR Wl
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iSaxton Nuclear. Experimental Corporation 2
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JAN 2 01987
REGION I==
Report No. 86-02 Docket No. 50-146 Category
License No. OPR-4 Priority
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Licensee:
Saxton Nuclear Experimental Corporation /GPU Corporation 1 Upper Pond Road Parsippany, New Jersey 07054 Facility Name: Saxton Reactor Inspection At: Saxton, Pennsylvania and TMI EOF, Harrisburg, Pennsylvania Inspection Conducted: November 6, 7, and 10, 1986 Inspector:
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/ 2. / 8h K. Weadock, Radiation Specialist date Approved by:
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M. Shanbaky, CMef, FacWities Radiation
'date Protection Section, EPRPB Inspection Summary:
Inspection on November 6, 7, and 10, 1986 (Report No. 50-146/86-02).
Areas Inspected: Announced, routine inspection by one region-based inspector of the decommissioned Saxton facility. Areas reviewed included procedures, records, and facility upkeep and radiological monitoring activities.
Results: One apparent violation, concerning a failure to make required notifications to the NRC, was identified.
(Section 3.0)
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Details 1.0 Persons Contacted 1.1 Licensee Personnel J. Auger GPUN/SNEC - PWR Licensing Engineer
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G. Baker SNEC General Manager
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W. Craft III SNEC Radiation Safety Officer
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J. Garry GPUN Environmental Controls
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1.2 NRC Personnel M. Shanbaky, Chief, Facilities Radiation Protection Section, EPRPB A. Weadock, Radiation Specialist 2.0 Purpose This was a preliminary inspection of records and radiological monitoring activities associated with the Saxton Nuclear Experimental Corporation (SNEC) reactor site.
This inspection was performed to review the current status of the Saxton site and ongoing custodial duties and monitoring activities. Areas reviewed included:
procedures and records,
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site monitoring activities.
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3.0 Procedures and Records On November 6, 1986, the inspector performed a review of Saxton site procedures, radiological surveys, and records maintained at the Three Mile Island Emergency Off site Facility (EOF) in Harrisburg, Pennsylvania.
During the course of this review one apparent violation, concerning a failure to make required notifications to the NRC, was identified.
Licensee Technical Specifications (T.S.) section 5, " Report", requires the licensee to notify the NRC of any occurrence of a "possible unsafe condi-tion".
Such notification should be made by telephone or telegraph with-in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of discovery, followed up by a written report within 15 days.
Technical Specifications section 5.a.3 requires such notification be made after any confirmed analysis of residual water from the Containment Vessel indicates activity concent-ation above the limits of Table II,10 CFR 20 limits for unrestricted release.
Review of radiological analysis results contained in the licensee's annual status reports indicated that, when present, water in the Containment Vessel sump generally exceeded 10 CFR 20 activity concentration limits for
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unrestricted release.
Cross-c ecking of licensee analysis results against notification reports to the NRC indicated that the required 15 cay written notification report was not submitted to the NRC for the following Con-tainment Vessel sump samples:
1.
A May 13, 1982 sample, identified in an addendum to the licensee's 1982 status report, 2.
A June 14, 1983 sample, identified in the licensee's 1983 annual report.
3.
A February 7, 1986 sample.
Analysis results for these samples and the corresponding 10 CFR 20 Appendix B Table II limits are included in attachment 1.
Failure to make the required 15 day written notification for the above samples constitutes an accarent violation of Technical Specification section 5.a.3 (146/86-02-01).
The inspector stated to the licensee that the potential for the above violation was identified in an internal licensee audit, completed in May, 1981, which identified that the licensee was not performing all analyses or making required reports to the NP.C.
The Saxton General manager provided the following additional information concerning the above analyses:
1.
The May,1982 sample was collected prior to the " official" 1982 second quarter facility surveillance, performed in June,1982.
The General Manager indicated that sample results may not have been reported since persor.rei at that time may have thought only the
" official visit" samples were required to be reported.
2.
Internal telepnene logs indicate that sample results for the June,1983 sample were communicated by phone to the individual responsible for making reports to the %C; however, the report apparently was then never generated.
3.
The licensee produced an internal file memo indicating that the results of the February 7,1986 sample were communicated by phone to the NRC on February 20, 1986. Although this memo indicates that a 15 day writter. notification report would be sent to the NRC, apparently no further act'on was taken.
The licensee also incicated that increased attention is now paid by both GPUN Environmental Controls and Licensing staff to insure all required notifications are made to the NR _
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The inspector also noted during reviews of Saxton annual status reports that the reported lower limit of detection (LLD) for Sr-90 was often greater tnan the 10 CFR 20 Appendix 8 Table II limit for unrestricted release.
The' licensee indicated that Saxton water samples were counted twice after collection; once by the TMI Unit 2 chemistry laboratory, followed by analysis at Teledyne, the licen-see's vendor laboratory. The licensee indicated that the LLD's included in the annual report were for the TMI laboratory, and that the subsequent analysis of samples at Teledyne was performed at substantially improved sensitivities such that all 10 CFR 20 limits could be detected. The licensee indicated, however, that a list of required LLD's would be submitted to the TMI Unit 2 lab to insure all preliminary analyses were sensitive enough to detect 10 CFR 20 limits. This memo was issued during the course of this inspection.
The inspector had no further questions in this area.
The inspector also reviewed surveys and facility inspection checklists from the completed quarterly site surveillances for 1986, 1985, and 1984.
No problems were noted and the licensee appeared to be meeting the requirements of their Technical Specifi-cations and procedure 9400-SUR-4523.01, " Quarterly Facility Inspec-tion Procedure".
The inspector noted that, although not required by their Technical Specifications, the licensee has been implementing a Radiological Environmental Monitoring Program (REMP) around the environs of the Saxton site. The inspector received copies of REMP monitoring results for 1982, 1983, and 1984 during this inspection.
Although time did not permit during the course of this inspection, these results will be reviewed and reported on during a subsequent inspection report (146/86-02-02).
4.0 Site Monitoring Activities On November 7, 1986, the inspector toured the Saxton site in Saxton, Pennsylvania and observed licensee quarterly surveillance activities.
The majority of radiological survey activities were performed in the Contain-ment Vessel; radiation and contamination levels were surveyed on the operating level as required. A physical and radiological examination was also made of the HEPA filter installed on the containment breather pipe.
The inspector noted that radiation levels were generally non-detectable on the operating level of the Containment Vessel. Contamination levels were generally also not detectable on this level, except for minimal levels found at the access area to the Contair. ment Vessel lower levels.
Licensee surveillance activities also included verification of the physical security of the site, tour of the buildings, and taking of water samples from the RWDF basement and pipe tunnel. The inspector noted that the condition of the auxiliary buildings at the site was generally very poor, due to age and weathering.
In particular, the Control and Administration
building was in an advanced state of disrepair; portions of the ceiling I
had fallen and there was evidence of wildlife infestation inside the buildin.
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Duplicate water samples from the RWDF basement and pipe tunnel and a soil sample taken from outside the exclusion area fence west of the Filled Drum Storage Area were obtained for NRC analysis during this inspection.
These results will be used for NRC review and comparison with the licensee's results only and do not represent or are intended to be part of a formal decommissioning sampling program.
Within the scope of the above review, no violations were noted.
Licensee onsite surveillance and monitoring activities appears adequate to meet Technical Specification requirements and support the current level of site activities. The inspector noted, however, that the level of monitoring effort will have to be commensurately upgraded as the status of site activities switches from custodial upkeep to dismantlement.
Exit Meeting The inspector met with licensee personnel denoted in Section 1 at the conclusion of the inspection on November 10, 1986. The scope and findings of the inspection were discussed at that time.
During this meeting the licensee also discussed upcoming plans for pumping residual groundwater from the RWDF basement to the Raystown branch of the Juniata River.
The licensee outlined sampling methodology and committed to informing the NRC Region I at the commencement of this activit.
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Attachment 1 J
Results of Containment Vessel Sump Water Analysis All results given in uCi/ml
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5/13/82-6/14/83 2/7/86 10 CFR 20, Appendix B*
Isotope sample sample Sample Table II, Col.2 limits
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Cs-137 1.3E-3 1.3E-3 1.9E-3 2.0E-5(S)
Cs-134 2.2E-5 1.5E-5 1.1E-5 9.0E-6(S)
'Sr-90 1.4E-5 4.8E-5 5.6E-5 3.0E-7(S)
- Values listed are the more restricted between soluble (S) and insoluble (I)
limits.
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