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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20202B2471998-02-0303 February 1998 Proposed Revised TS in Response to 980127 RAI Re TS Change Request 59 ML20210Q2291997-08-21021 August 1997 Proposed Revised Tech Specs Re TS Change Request 59 ML20140C1441997-05-30030 May 1997 Proposed Revised TS Pages Re Decommissioning ML20134P3941996-11-25025 November 1996 Proposed Decommissioning TSs ML20112E8151996-05-17017 May 1996 Proposed Decommissioning TS Pages ML20094Q0691995-11-21021 November 1995 Proposed Tech Specs for Transfer of mgt-related Responsibilities for Plant from SNEC to Gpun ML20086A5791995-06-23023 June 1995 Proposed Tech Specs Pages 1,2 & 8,changing Organization Performing Remainder of Characterization Activities & Future Decommissioning Activities to Assure Linkage W/Licensee Appropriately Maintained ML20084J3381995-06-0202 June 1995 Proposed Tech Specs,Reflecting Proposed Changes to TS App a Per TS Change Request 56 ML20072C2481994-08-0808 August 1994 Proposed Tech Specs,Revising Existing Content & Format & Analysis Applying Stds of 10CFR50.92 in Making Significant Hazards Considerations Determination ML20062L8501993-12-20020 December 1993 Revised TS Pages Re Location,Exclusion Areas,Principal Activities & Administrative & Procedural Safeguards ML20045G7031993-06-23023 June 1993 Proposed TS A-4.3 Re Principle Activities Permitted by TS ML20094P0471992-04-0202 April 1992 Proposed TS Change Request 53,Rev 3 to License DPR-4, Removing Reactor Support Bldgs/Structures from TSs ML20090G8781992-03-0606 March 1992 Rev 2 to TS Change Request 53 to Amend License DPR-4, Requesting Removal of Reactor Support Bldgs & Structures from TSs ML20235H0441987-09-22022 September 1987 Proposed Tech Specs Change 53,reflecting Removal of Outbuildings & Structures ML20085D5831964-02-29029 February 1964 Proposed Tech Specs for Saxton Nuclear Experimental Corp ML20085D0701963-01-18018 January 1963 Proposed Rev of Suppl 1 to Tech Specs Re Automatic Switching of 440 Volt Buses During Operation of Safety Injection Pump ML20085C6331962-01-0505 January 1962 Proposed Tech Specs Re 5-yr R&D Program 1998-02-03
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20206F6801998-04-22022 April 1998 Rev 0 to 6575-PLN-4542.08, ODCM, for SNEC ML20202B2471998-02-0303 February 1998 Proposed Revised TS in Response to 980127 RAI Re TS Change Request 59 ML20202F7111998-02-0202 February 1998 Rev 1 to 1000-PLN-3000.05, Saxton Nuclear Experimental Corp Facility Decommissioning QA Plan ML20211C2521997-09-16016 September 1997 Rev 0 to Procedure 6575-PLN-4542.09, SNEC Facility Process Control Program ML20210Q2291997-08-21021 August 1997 Proposed Revised Tech Specs Re TS Change Request 59 ML20140D2611997-06-0303 June 1997 to SNEC Facility Offsite Dose Calculation Manual ML20140C1441997-05-30030 May 1997 Proposed Revised TS Pages Re Decommissioning ML20134P3941996-11-25025 November 1996 Proposed Decommissioning TSs ML20112E8151996-05-17017 May 1996 Proposed Decommissioning TS Pages ML20094Q0691995-11-21021 November 1995 Proposed Tech Specs for Transfer of mgt-related Responsibilities for Plant from SNEC to Gpun ML20100H6231995-11-10010 November 1995 Rev 0 to Program 6250-PGD-2720, Engineering Support Personnel Training ML20100H6311995-11-0909 November 1995 Rev 0 to Procedure 6575-ADM-4500.07, SNEC Procedure Development,Change Requests & Safety Reviews ML20086A5791995-06-23023 June 1995 Proposed Tech Specs Pages 1,2 & 8,changing Organization Performing Remainder of Characterization Activities & Future Decommissioning Activities to Assure Linkage W/Licensee Appropriately Maintained ML20084J3381995-06-0202 June 1995 Proposed Tech Specs,Reflecting Proposed Changes to TS App a Per TS Change Request 56 ML20107K0801995-04-20020 April 1995 Control of Hotwork ML20116A0811995-03-13013 March 1995 Rev 0 to Procedure 6575-PLN-4520.06, SNEC Site Characterization Plan ML20115K1141994-11-0101 November 1994 Rev 0 to Procedure 6575-PLN-4542.02, SNEC Soil Erosion & Sedimentation Control Plan ML20116A0731994-09-14014 September 1994 Rev 4 to Procedure 6210-ADM-2621.02, Maint Training Instructors ML20072C2481994-08-0808 August 1994 Proposed Tech Specs,Revising Existing Content & Format & Analysis Applying Stds of 10CFR50.92 in Making Significant Hazards Considerations Determination ML20062L8501993-12-20020 December 1993 Revised TS Pages Re Location,Exclusion Areas,Principal Activities & Administrative & Procedural Safeguards ML20078A2701993-12-0303 December 1993 Rev 1 to Procedure 6575-SUR-4523.01, Quarterly Facility Insp Procedure ML20045G7031993-06-23023 June 1993 Proposed TS A-4.3 Re Principle Activities Permitted by TS ML20094P0471992-04-0202 April 1992 Proposed TS Change Request 53,Rev 3 to License DPR-4, Removing Reactor Support Bldgs/Structures from TSs ML20090G8781992-03-0606 March 1992 Rev 2 to TS Change Request 53 to Amend License DPR-4, Requesting Removal of Reactor Support Bldgs & Structures from TSs ML20090G8931992-03-0404 March 1992 Rev 0 to 6675-PLN-4542.01, Radiation Protection Plan ML20078A2621991-10-14014 October 1991 Rev 1 to Procedure 6675-ADM-4500.07, SNEC Procedure Development,Change,Requests & Safety Reviews ML20085C5001991-10-0202 October 1991 Procedure for Conducting 24 H Leak Rate Test ML20235H0441987-09-22022 September 1987 Proposed Tech Specs Change 53,reflecting Removal of Outbuildings & Structures ML20085C4491971-06-17017 June 1971 Containment Vessel Leakage Rate Determination by Absolute Method ML20085F5931968-02-28028 February 1968 High Radiation Evacuation Plan ML20085D5831964-02-29029 February 1964 Proposed Tech Specs for Saxton Nuclear Experimental Corp ML20085D2611963-06-10010 June 1963 Chemical Shim Test 308.3, Chemical Shim Control Under Nucleate Boiling Conditions ML20085D0701963-01-18018 January 1963 Proposed Rev of Suppl 1 to Tech Specs Re Automatic Switching of 440 Volt Buses During Operation of Safety Injection Pump ML20085C6331962-01-0505 January 1962 Proposed Tech Specs Re 5-yr R&D Program ML20085C6161961-11-15015 November 1961 Preoperational Tests ML20085F5871961-11-0101 November 1961 Plan for Hosp Reception of Radiation Casualties ML20085C5921961-08-17017 August 1961 Preoperational Test 304C, Component Cooling Sys Operational Test 1998-04-22
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'A. SITE-
- 1. Location The Saxton site is a 1.148 acre tract deeded from the Pennsylvania Electric Company to the Saxton Nuclear Experimental Corporation (SNEC). It is located within the property of the Pennsylvania Electric Company near the Borough of Saxton, Pennsylvania, in Liberty Township, Bedford County, Pennsylvania. The Pennsylvania Electric Company property consists of approximately 150 acres along the Raystown Branch of the Juniata River.
- 2. Exclusion Area Controls
- a. The exclusion area consists of that portion.of the Saxton Nuclear Experimental Corporation property enclosed within the ,
fence containing the Containment Vessel. See Figure 1.
- b. Except for authorized entry the following access points shall i be maintained locked:
- 1) -the gates to the Exclusion Area fence surrounding the l Containment Vessel,
- 2) the Containment Vessel access door, I
- 3) the grating covering the Auxiliary Compartment stairwell in the Containment Vessel, i i
- 4) and the Rod Room door. !
- c. The Containment Vessel shall be equipped with an intrusion alarm to supplement the multiple physical barriers to '
intrusion.
- d. Employees of the Pennsylvania Electric Company's Line Department headquartered on the Penelec property shall report '
to the Vice President SNEC Programs / Program Director Saxton Nuclear Experimental Facility (SNEF) or the designated i 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. Principal Activities Pennsylvania Electric Company personnel associated with electric power transmission and maintaining electric power distribution equipment are headquartered on the Pennsylvania Electric Company property. Activities permitted within the Exclusion Area shall . !
include routine and emergency. inspections, maintenance associated J with the possession of the Saxton Reactor Facility and !
characterization activities associated with the decommissioning of I 1
the facility.
l 9507030291 950623 PDR P ADOCK 05000146 PDR
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B. ADMINISTRATIVE AND PROCEDURAL CONTROLS i Administrative controls relate to the organization, activities, procedures, record keeping, reporting and review and audit considered necessary to provide assurance and evidence that activities within the I Exclusion Area are managed in a safe manner. Procedure controls are applicable to activities for which it is considered necessary to provide assurance that they are performed in a safe manner.
- 1. Organization 1 SNEC has the responsibility for safely maintaining the Containment Vessel and performing the characterization activities in support of its i decommissioning. The organizational structure with reporting and communications lines is depicted in Figure 2.
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- a. The responsibilities of management and supervisory level personnel are as follows:
- 1. SNEC President provides management oversight for all Saxton {
activities and reports to the SNEC Board of Directors. !
- 2. President GPUNC provides full-time dedicated management for the purpose of conducting all nuclear activities safely and effectively.
The Executive Vice President SNEC and Vice President Nuclear Services Division assures that all division and corporate activities are performed in accordance with corporate policies, applicable laws, regulations, licenses and technical specifications. ,
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- 3. Vice President SNEC Programs / Program Director SNEF is responsible l l for administration of all SNEC functions, direction of all ;
decontamination and characterization activities and for assuring that the requirements of License No. DPR-4 and these Technical Specifications are implemented.
- 4. SNEC Radiation Safety Officer (RS0) is responsible for the conduct and oversight of all Saxton Radiation Safety Activities through implementation of the SNEC Radiation Protection Plan. All radiological controls. personnel shall have stop work authority in matters relating to or impacting radiation safety.
- 5. Group Radiological Controls Supervisor (GRCS) directly supervises radiation safety activities. The position reports to the RSO.
- 6. The SNEF Site Supervisor reports to the Vice President SNEC Programs
/ Program Director SNEF. The Supervisor provides on-site management and continuing oversight of production activities.
- b. Other GPUN Division personnel provide SNEF management with technical l support and project management capabilities.
- c. Staffing requirements are as follows:
- 1. At least two individuals, one of which must be I knowledgeable in radiation monitoring and the radiological l 2
Figure 2 ( ',
SNEC Board of Directors ,
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l President SNEC
_____________________________________p I
l l l I I I l
l Executive Vice President SNEC and Other GPUN
+___ a abon Safeh Division Support Nuclear Safety I Vice President Nuclear Services .i
l Communications Department l
I l Engineering Vice President SNEC Programs / 4__j Radiation Safety --- -------- -- -k Program Director SNEF Officer l Information Management SNEF Legal Group RadiologicalControls Supervisor (as needed)
! Key-Direct reporting relationship Radiological Controls Other Services -------
Indirect reporting relationship Technicians (as needed) Division Departments 8
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