ML20235H044
| ML20235H044 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 09/22/1987 |
| From: | SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | |
| Shared Package | |
| ML20235H020 | List: |
| References | |
| NUDOCS 8709300345 | |
| Download: ML20235H044 (7) | |
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Technical Specification Change Reauest No. 53 SNEC reauests that the attached revised pages and figure replace the following pages and figure of the current Saxton Technical Specifications (Tech Specs).
Replace A-1, A-2, A-3, A-4 and Figure 1 II.
Reasons for Change This TSCR proposes to remove the Saxton Nuclear Facility i
outbuildings and structures f rom the Saxton Tech. Specs. The I
outbuildings and structures involved are the Control and Auxiliary Building (C&A Bldg.), the Radioactive Waste Disposal Facility (RWDF), the Refueling Water Storage Tank, the earthen Filled Drum Storage Area and the Pipe Tunnel.
The Containment Vessel (CV) will not be affected by this change.
The TSCR also proposes to make minor editorial changes, to accurately reflect the NRC management for this facility and to accurately reflect the improved water analysis methods employed by SNEC.
III.
Safety Evaluation and Justification of Changes In May of 1972, SNEC endt; power operations at the Saxton Nuclear Facility. Decommissioning and/or maintenance of the facili*; was begun and has continued since then.
SNEC is currently in the process of ensuring that the outbuildings and structures (excluding the CV) at Saxton are decontaminated to acceptable levels.
This is being accomplished with Health Physics controls in place to satisfy Section 4.d of the Technical Specifications and performed within the requirements of Section 3.e of the Technical Specifications associated with the Saxton Decommissioning Plan and Final Safeguards Report. Therefore, this work will be accomplished in accordance with regulatory requirements.
However, as an additional step well beyond these requirements SNEC intends to follow NRC guidelines for decommissioning per NRC Regulatory guide (R.G.) 1.86, " Termination of Operating Licenses for Nuclear Reactors". SNEC will assure that the endpoint criteria of RG 1.86 are met by performing a detailed radiological survey of the outbuildings and structures.
Once this is confirmed by NRC, then the outbuildings and structures would be eligible for release for unrestricted use in accordance with the guidance of R.G. 1.86, Section 4.
The residual contamination remaining in the outbuildings and structures would be at or below the R.G.1.86 criteria and therefore, by existing NRC guidance, will not adversely affect the health and safety of the public.
It is thus concluded that the removal of the outbuildings and structures at Saxton (excluding the CV) from the Saxton Tech.
Specs., is not a safety concern and will not have any adverse impact on the health and safety of the general public.
Further, because the residual contamination levels included are lower than those evaluated in the Saxton Final Safeguards Report and are in accordance with R.G. 1.86, it is concluded that no unreviewed safety question exists.
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IV.
No Significant Hazards Consideration
.These proposed changes are most similar to Example (iv) of
~" Amendments Not Likely to Involve Significant Hazards Considerations", Federal Register Volume 48, No. 67 at 14870,' dated April 6,1983. A no significant hazards consideration determination is proposed for this TSCR_because:
1)
The proposed changes do not involve a significant increase in-the probability or consequences of an accident previously evaluated. The proposed changes involve removing structures from the Saxton Technical ~ Specifications which have been decontaminated to levels consistent with existing Tech. Specs.
and published NRC guidelines for termination of' operating licenses.
These NRC established levels relate to radionuclides amounts far less than those used for accident analyses in the Saxton Final Safeguards Report. As such, by decontamination of the structures, the consequences of an accident have actually been reduced.
2)
The proposed changes do not create the possibility of a new or L
different kind of an accident.
The release of structures which have been decontaminated to levels consistent with NRC guidelines _for release of structures does not create the possibility of a new or different kind of accident.
3)
The proposed changes do not involve a significant reduction in i
a margin of safety. -The' release of the structures is in l
accordance with NRC release guidance.
The NRC release guidance was established to prevent risk to the public health and safety.
V.
Implementation In order to continue work activities at the site in a productive manner, it is reouested that the Amendment authorizing these changes be issued by December 1, 1987.
VI.
Amendment Fee (10CFR 170.21)
Pursuant to the provisions of 10CFR 170.21, attached is a check for
$150.00.
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4 l
.A.
SITE L
1.
Location The f acility shall be located within the property of the Pennsylvania Electric Company near the Borough of Saxton, Pennsylvania, in Liberty Township, Bedford County, Pennsylvania.
l The Pennsylvania Electric Company property shall consist of approximately 150 acres along the Raystown Branch of the Juniata River.
2.
Exclusion Areas (Figure 1)
The exclusion area shall consist of:
l An area within the Pennsylvania Electric Company property
.which is enclosed within a fence and contains the Containment Vessel.
3.
Principal Activities l
The principal activities carried on within the Pennsylvania l
Electric Company property shall be the headquarters for personnel I
associated with maintaining the electric power distribution equipment and the transmission of electric power by the Pennsylvania Electric Company.
The only activity carried on within the Exclusion Area shall be routine and en.ergency inspections and maintenance associated with the possession of the decommissioned Saxton Nuclear Facility.
B.
ADMINISTRATIVE AND PROCEDURAL SAFEGUARDS 1.
Administrative Organizations The General Manager of the Saxton Nuclear Experimental Corporation (SNEC) shall have the responsibility for administration of all SNEC functions and for assuring that the requirements of License No. DPR-4 and these Technical Specifications are implemented.
2.
Controls a.
Except for authorized entry, the gate to the Exclusion Area surrounding the Containment Vessel shall be maintained locked, the Containment Vessel access door shall be maintained locked and shall be eauipped with an intrusion alarm, the grating cover over the Auxiliary Compartment stairwell in the Containment Vessel shall be maintained locked, and the Rod Room door shall be maintained locked.
A-'I
r b.
Employees of the Pennsylvania Electric Company's Line Department headquartered on the Penelec property shall report to the SNEC General Manager or his designated representative any observed indication of change in the facility status as shown by smoke, fire, tornado, flood, or attempted break-in and take any immediate action authorized.
3.
Records In addition to the records reauired by applicable NRC regulations, including Section 20.401 of 10 CFR Part 20, SNEC shall keep the following:
a.
Records of inspection of the decommissioned facility including the results of surveys of radioactivity levels and as-found and as-left conditions of the facility.
b.
Records of entries into the Containment Vessel and reason for entry.
c.
Dates of Quarterly inspections and evaluation of the results.
d.
Records showing radioactivity released or discharged into the air or water beyond the effective control of SNEC as measured at or prior to the point of such release or discharge.
e.
Records of design changes and maintenance necessary to maintain the decommissioned f acility as described in the Saxton Decommissioning Plan and Safety Analysis Report as revised by SNEC letter dated May 31, 1974.
4.
Periodic Inspections a.
A definite inspection schedule shall be established for the f acility that will be performed by personnel knowledgeable in nuclear radiation monitoring and the radiological hazards associated with the facility.
Inspections will be conducted concurrently with radiation monitoring. The frecuency of these inspections shall be no less than cuarterly.
The s
records of these inspections shall be maintained on file.
b.
The Health Physics inspection shall include a survey of radiation levels and surface contamination in the Containment Vessel.
The filter on the ventilation " breather" pipe from the Containment Vessel shall also be changed and counted for activity as a measure of the activity available for release.
The Containment Vessel shall be inspected at the lowest level for water.
If water is found, a sample shall be taken and shall be subjected to gamma spectral analysis.
A-2
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c.
All reouired maintenance work shall be performed under Health Physics control to minimize any possible radiation exposure i
involved.
If entry into the controlled area of the containment should be necessary, radiation levels, and airborne activity surveys shall be obtained prior to beginning work. All work shall be performed under controls consistent with 10 CFR Part 20 requirements to minimize radiation exposure of personnel and to prevent the release of radioactivity to the environment.
d.
All radiation surveys, tests, counting work, and radiation exposure control measures shall be performed in accordance with written instructions and procedures that conform with the requirements of the "Saxton Nuclear Facility Radiation Protection Plan." Facility inspections, access control, and emergency actions shall be in accordance with written procedures.
5.
Reports In addition to those reports required by applicable NRC regulations, SNEC shall submit the following:
i a.
A report of any occurrence of a possible unsafe condition relating to the f acility or to the public.
For each occurrence, SNEC shall promptly, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of discovery, notify by telephone or telegraph the Administrator of Region I, or his designee, and shall submit a written follow-up report within 15 days which describes the circumstances and the corrective action taken.
These reports shall include:
(1) Any unplanned or uncontrollable release of radioactive material from the facility.
(2) Conditions arising from natural or man-made events that affect the integrity of the Containment Vessel.
(3) Any confirmed analysis of residual water from the Containment Vessel which indicates that the activity concentration is above the limits of Table II,10 CFR Part 20 for unrestricted release.
b.
An annual report to the Director, Office of Nuclear Reactor Regulation, of the status of the deactivated facility including:
(1) Information relating to changes in those staff positions that are designated as being responsible f or the deactivated facility.
A-3
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(2) A summary of entries into the Containment Vessel and reasons for entry.
(3) A summary of maintenance and design changes made to the deactivated facility.
(4) Results of surveys of radioactivity levels and of water sample analyses.
(5) A review of the performance of access control and surveillance measures.
A-4
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