ML20094P030

TS Change Request 53,Rev 3 to License DPR-4,removing Reactor Support Bldgs & Structures from TSs

ML20094P030
Person / Time
Site:	Saxton File:GPU Nuclear icon.png
Issue date:	04/02/1992
From:	Hildebrand J SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
Shared Package
ML20094N988	List: ML20094N985 ML20094P030 ML20094P047
References
NUDOCS 9204070167
Download: ML20094P030 (6)

Text

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SAXTON NUCLEAR EXPERIMENTAL CORPORATION SAXTON NUCLEAR FACILITY l Operating License No. DPR-4 Docket No. 50-146 )

Technical Specification Change Request No. 53 Rev. 3 )

This technical Specification Change Request is submitted in support of Licensee's request to change Attachment A to Operating License No. DPR-4 for the Saxton Nuclear Facility. As a part of this request. proposed replacement pages for Attachment A are also included.

SAXTON NUCLEAK EXPERIMENTAL CORPORATION BY: A. t' .b A t el President, SNEC Sworn and Subscribed i

to before me tpis cN rld 1 day oE(J  !

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I A&R- 61.1rd/ dado

' Notary Public OtANA M. DeBLASIO

% ARY PtlBLIC OF NEW ERSEY u, n,emnstv Exinm C /S146 y

l 9204070167 920402 PDR l ADOCK 05000246 PDR 30192009.lat

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF SAXTON NUCLEAR EXPERIMENTAL CORPORATION DOCKET No. 50-146 LICENSE NO. DPR-4 CERTIFICATE OF. SERVICE This is to certify that a copy of Technical specification Change Request No. 53,_Rev. 3 to Attachment A of the Operating License for the Saxton Nuclear Facility has, on the date given below, been filed with executives of Liberty Township Bedford County Pennsylvania; Bedford County, Pennsylvania; and the Pennsylvania Department of Environmental Resources, Bureau of Radiation Protection, by deposit in the United States mall, addressed as follows:

Mr. Donald Weaver, Chairman Mr. Richard Rice, Chairman Liberty Township Supervisors Bedfctd' County Commissioners R.D. #1 County Courthouse Saxton, PA 16678 203 South Juliana Street i

Bedford, PA 15522

Mr. William Dornsife, Director SAXTON NUCLEAR EXPERIMENTAL CORP. -

PA. Dept. of Environmental Resources Mildt cn Bureau of-Radiation Protection BY: I b<d P.O.-Box 2063 President, SNEC

- Harrisburg. PA 17120 DATE: f2 l

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1. Technical _Srecification Channe Request No, $3 The Saxton Nuclear Experimental Corporation (SNEC) requests that the following revisions be made to the SNEC Technical Specifications (TS):

Replace pages A-1, A-2, A-3.-A-4, and Figure 1.

II, Reasons For Chance This Technical Specification Change Request (TSCR) requests NEC authorization to remove the SNEC f acility reactor support buildings and structures from the SNEC TS. The reactor support buildings and-st ructures covered by this TSCR are the Control and Auxiliary (C&A) building, the Radioactive Waste and Disposal Facility (RWDF) building, the Refueling Water Storage Tank, the carthen filled Drum Storage Area, and the Pipe Tunnel. Additionally.- this TSCR clarifies numerous sect ions in the TS, while deleting others.

The reactor Containment Vessel (CV) is not affected by this TSCR.

The changes

• o the current TS are sunrnarized below:

TS A.1 has been revised for clarity, TS A.2 has been revised to reflect that the exclusion area is within the SNEC property, and delete reference to the C&A and RWDP buildings, since ,

o .. they are being removed under this TSCR.

TS A.3 has been revised to reflect that principal activities are carried on within the Pennsylvania Electric Company property and not the Saxton Steam Generating Station property.

TS B.2.a has been ravised to reflect that the ' gate" to the exclusion area surrounding the CV shall be maintained locked.

TS B.2.h has been deleted since the kWDF wili-be removed by this TSCR.

TS-B.2.c has been deleted since the C&A building will be removed by this TSCR.

TS 8.2.d has been revised to replace the term "SSGS," which refers to -

the Saxton Steam Generating Station, with t.he term "PENELEC." This section has also been redesignated as TS B.2.b, under this TSCR.

TS B.3.b has been revised to refer to the Containment Vessel only, since-it will be the only building remaining.

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Tb B.4.b has been revised t o r equire t hat only the Cont ainment Vessel shall be inspected at the lowest level for water. Reletence to the RWDF building has been deleted since it will be r emoved unde r t his TSCR, This section has also twen revised to require that a ganma-spectral analysis be performed for any water found at the lowest level of the Containment Vessel. The revision also deletes the requirement to analyze for gross Beta activity, A gammm-s pec t ral atu l ys i s providrs a more accurate and useful desc r ipt ion of the radiological chataitetistits of the sump water t han does gross Beta analysis.

TS B.4.d has been re/ised to refer to the Saxt on Nuc lea r l'aci lit y Radiat ion Pr otection Plan Instead of the Saxton Nuclear Experimental Reactor Facility Radiatien Protectten Manual.

i T5 B.S.a has been revised to indicate that the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification will be made to the Administrator of Region 1, and the NRC Uperations Centt r, and that the writ ten tollow up report will be sent to the Documtat Control Desk and the Administ rat or of Region 1.

TS B 5.a.2 has been revised to refer to the Containment Vessel only, since it will be the only structure temaining.

TS B.S.1. has been deleted. This section required a 24 hour notification followed by a 15 day written report when a confirmed analysis of residual water f rom t he Containment Vessel or RWDF building indicated that the activit y concentration is above the limits of Table II, 10 CFR part 20 f or unrest ricted release.

Generally, on a quarterly basis, the confirmed value for some i sot opes inside the containment vessel exceeded the limits in Table II and were reported, as required. However, this is routinely expected due to the condensation which collects in the sump. The sump watet poses no threat to the health and safety of the public or to the environment because there are no release paths to the external environment from the .

C on t a illme n t Vessel Sump The water in the sump originates from condensation on the inside of the Containrwnt Vessel, and is a consequence of a hieather pipe which was installed to permit the vessel t o breathe with changes in atmosphetic conditions. As such, there is no safet3 concern and this administ rat ive reporting requi ren < nt for this normal and routine condit ion may be deleted. SNEC will continue to periodically monitor, on a quarterly basis, the contalnment vessel sump water and report iti find!'gs in the re<,uired annual report.

TS R.S.h has been revised ta include a t ime limit f or submit t al of the required Annual Report to the NRC. nlso, reference to the Director, Division of Reactor Licensing, has been replaced with the Document Control Desk and the Administrator of Region I.

TS B.5.b.2 has been evised to delete reference to the RWDF building since it will N- rem ed by this TSCR.

TS Finuro I has been res' 'o show t h- new fence . rec t ed in front of the ChA buiIding.

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1I1. Sa fet y Evaltta t i on In May 1972, the SNEC facility ended power operation and decommissioning and/or maintenance of the facility was begun and has continued since then.

Decontamination was performed in 1987 19 8 8, a tid 1989 to ensure t hat residual ccntamination was as low as reasonably achievable A comprehensive final release ;urvty was conducted from October 1988 to June 1989 to verify that residual mntamination was within NRC guidelines for unrestricted use. Sur f ace cont aminat ion measurement s were cor pat ed t o Rt gulat ory Guide 1.86 "Terminat ion of Opet at ing Lit enses for Nuclesr Reactors."

The survey results shewed t hat the residual radioactivity it less than the NRC guidelines for 'inrestricted use. The final release sutvey result s were su!citted to the hRC in 1990 and 1991.

An independent confirmatory sutvey la s performed by Oak Ridge Associated University (0RAU) f or the NRC during October 1990 and the'r >eport submitted to the NRC in June 1991. 5 The ORAU report states that the results of the con f i rmat ory survey support the findings of the final survey performed by GPUN, and, in ORAU's opinion, confirm that the decent aminat ion et t ort s have been successful in satisfying NRC guidelines for release f or unrest rit t ed use for the C&A building, RWDF building, and pipe tunnel of t he SNEC faellity. Additional information requested by the NRC in response to ORAU queries were also sat is f act orily addr essed by SNEC, It should be noted that several areas were identliied by SNEC as hold points, since they were inaccessible during the final telease survey.

These areas wi11 be surveyed and dispositioned during dismautlement and demolition. Tne NRC will be notified of the st atus of each hold point and given the option to review the results before f inal disposit lon.

Based on the above discussion, as supported by the referenced reports, it is evident that the reactor support buildings atul si ructures at the SNEC facility are decontaminated to acceptable levels. As such, the buildings md st ructures covered by this TSCR ate eligibic for release for unrestricted use, since they do not pose a nuclear ety concern. ,

Their removal f rom t he TS will not have any adverse impac. o.. ,_ h e health and saf ety of t he public.

. .s IV. No Si cni f ic ant Ha z a rils Concideration SNEC has determined that the TSCR poses no signif ic ant hazards as de fined in 10 CFR '50.42. Unrestricted release and removal of the C&A huilding, RWDF building, Re fueling Wat e r Storage Tank, the eatthen filled Drtim Storage Area, and the Pipe Tunnel f rom t he TS in accordance with the proposed TSCR wi11 not:

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1. Involve a significant increase in the probability or consequences of -l an accident previously evaluated. The SNEC facilit y ended power j operation in May 1972. The reactor support buildings and situctures ,

covered by this TSCR are not operational, and have been decontaminated to levels consistent with published NRC guidelines. l The reactor support buildings and structures are not susceptible to any nuclear accident. Hence, there is no increase in the probabi1ity -

or consequences of any accident previously evaluated.

2. Create the possibility of a new or different kind of accident from any accident previously evaluated. The reactor support buildings and structures covered by this TSCR are not operational and have been decontaminated to levels consistent with published NRC guidelines for termination of operating Ilcenses. As such, the proposed change coverud by this TSCR does not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Involve a significant reduction in a margin of safety. The reactor support buildings and structures covered by this TSCR are not operational and have been decontaminated to levels consistent with published NRC guidelines for termination of operating licenses. As such, there is no reduction in a margin of safety, i

i V. Imril emen ta t ion It is requested that the amendment authorizing this TSCR be issued expeditiously and be effective upon issuance to enable SNEC to physically remove the reactor support buildings and structures covered by this TSCR.

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