ML18040A830
| ML18040A830 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 03/26/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18040A829 | List: |
| References | |
| NUDOCS 8704020381 | |
| Download: ML18040A830 (5) | |
Text
~R,S RECT UNITEDsi ATE" NUCLEAR REGULATORY CQI.1/v!!SSlON WASHINGTON, D. C. 20555
,.A,.>> SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION IB**~+
SUPPORTING AMENDMENT NO.
TO FACILITY OPERATING LICENSE NO. NPF-14 AND AMENDMENT NO. 33 TO FACILITY OPERATING LICENSE NO. NPF-22 PENNSYLVANIA POWER 5 LIGHT COMPANY SUS UEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 DOCKET NOS. 50-387 AND 50-388 I.O INTRODUCTION By letter dated October 17,
- 1986, Pennsylvania Power and Light Company (PP8IL) submitted, for staff review and approval, two revisions to the Susquehanna Physical Security Plan.
The first revision involves the discontinuation of updating all security clearances every eight years and the second relates to changing the designation of the non-safety related condensate transfer arid storage system to a non-vital status.
Securit Clearance U dates The Commission's Regulation 10 CFR 73.55 for requirements for physical protection does not specifically require security clearance updates for licensee employees who are authorized unescorte'd access to protected and vital areas.
In the absence of specific regulations, the NRC has historically requested that facilities commit to American National Standard ANSI N18.17-1973, which specifies a limited background investigation, an examination by a licensed psychiatrist or physician to identify aberrant be-'avior, and a continued observation program to detect aberrant behavior.
There are no provisions in the Standard for clearance updating.
On August I, 1984, the NRC published in the Federal Register (49FR30727) proposed amendments to 10 CFR Parts 5C arid 73 of its.reaulations which would establish an employee screenina program for individuals requiring unescorted access.
The NRC has since withdrawn that proposed regulation and is preparing a policy statement which will replace the proposed rule with an industry-proposed initiative for an access authorization program.
This initiative is sponsored by the Nuclear UtilityManagement and Resource Committee (NUMARC).
The recommended NUMARC guidelines contain no provision for updating active security clearances.
Vital E ui ment Identification The Safety Evaluation Report (SER) prepared by the NRC on December 7, 1983, contained a discussion and review of vital equipment as it pertained to the licensing of both units.
The design basis for the licensee's program for identifying vital equipment included the regulatory definition of vital, Part 100 release limits, and the criteria contained in Regulatory Guide 1.29 and Review Guideline Number 17.
The program used conservative assumptions (i.e.,
no credit is given for offsite power and equipment not protected as vital is assumed to be unavailable) and a detailed plant analysis (fault tree) to identify both single, items of equipment and combinations that require pro-tection as vital.
870402038i 87032b PDR ADOCK 05000387 P-...,
In a Safeguards Information Appendix attached to that document, the NRC listed the eouipment and areas considered to be vital.
The Appendix specifi-cally notes that the condensate storage tank need not be considered vital equipment.
Generica11y, condensate storage and distribution systems are not considered to be vital at most boiling water reactors.
2.0 EVALilATION The licensee's Security Plan presently requires that employee Security clearances be updated every eight years.
The licensee states that the cost of such routine security clearance updates is substantial.
The licensee proposes that since security c1earance updates are not required by the Commission's regulations the security plan be amended to eliminate this requirement.
The licensee will retain a security plan option to conduct a clearance rescreening if at any time there is cause to suspect adverse changes in an employee's trustworthiness or reliability.
Accord-ingly, because this change is only an extension of past and present industry practices, no additional risk is introduced.
The staff finds'he proposed change acceptable.
The request by PPSL to no longer designate the condensate transfer and storage system as vital does not require any procedural or design changes.
These changes are only administrative in nature and do not involve any safety re-lated equipment or functions.
As previously noted, this position was accept-able to the NRC as stated in its December 7, 1983, Safety Evaluation Report, and, accordingly remains acceptable, since no additional risk'is introduced.
3.0 ENVIRONMENTAL CONSIDERATION
These amendments relate solely to safeguards matters and do not.involve any sianificant construction impacts.
Accordingly, these amendment meet the eliaibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(12).
Pursuant to 10 CFR 51.22(b),
no environmental impact state-ment or environmenta1 assessment need be prepared in connection with the issuance of these amendments.
4.0 CONCLUSION
The Commission made a proposed determination that the amendments involve no significant hazards consideration which was published in the FEDERAL REGISTER (51 FR 47084I on December 30, 1986, and consulted with ttte state ouf oennsylvania.
No public cosments were received, and the state of Pennsylvania did not have any comments.
The staff has concluded, based on the consideration discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed
- manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security nor to the health and safety of the public.
Principal Contributors:
R. F. Skelton, NMSS E. McPeck, NRR Dated:
March 26, 1987
SUSOUEHAHHA STEAM ELFCTRIC STATION UNITS 1 AND 2 CHRONOLOGY OF THF. APPROVED PHYSICAL SECURITY PLAN'S EVOLUTION The approved-security plans for the Susquehanna Steam Flectric Station Units 1
and 2 consist of the following amendments, revisions and chanaes:
"Susquehanna Steam Electric Station Physical Security Plan"
- Change A, dated July 31, 1978 (by letter dated July 31, 1978) as revised by:
- Change 8, dated February 15, 1979 (bv letter dated February 15, 1979>
- Change C, dated Auaust 15, 1979 (by letter dated Auaust 23, 1979>
- Chanqe D, dated September 28, 1979 (bv letter dated October 8, 1979)
- Chanae E, dated May 22, 1980 (by letter dated July 11, 1980~
- Change F, dated March 27, 1981 (bv letter dated April 8, 1981>
- Change 6, dated May 29, 1981 (by letter dated June 5, 1981)
- Chanae H, dated June 26, 1981 (by letter dated June 29, 19811
- Chanae I, dated March 19, 1982 (by letter dated March 26, 1982>
- Chanae 1, dated April 1, 3982 (by letter dated April 23, 1982)
- Change K, dated May 4, 1982 (by letter dated May 5, 1982)
- Chanae L, dated July 9, 1982 (bv letter dated July 13, 1982)
- Change M, dated October 15, 1982 (by letter dated October 25, 1982)
- Chanae N, dated April 25, 1983 (by letters dated May 6 and October. 26, 1983)
- Chanqe 0, dated June 15, 1983 (by letter dated June 16, 1983)
- Chanae P, dated June 24, 1983 (by letter dated June 27, 1983>
- Change 0, dated November 30, 1983 (by letter dated December 2,
1983)
- Change R, dated January 31, 1984 (by letter dated February 21, 1984)
- Change S,
NO DATE (by letter dated May 3, 1984)
- Change T, dated Januarv 15, 1985 (by letter dated January 15, 1985)
- Change U, dated March 15 and May 17, 1985 (bv letters dated t)ar'ch 15, and May 17, 1985)
- Change V, dated October 3, 1985 (by letters dated October 14, l985 and March 26, 1986)
- Chanae M, dated July 15, 1986 (by letters dated July 22 and Auaust 18, 1986'I
- Change N, NA OATE (by [[letter::05000388/LER-1986-013-01, :on 860919,full Reactor Protection Sys Scram Occurred When Intermediate Range Monitors C & G Spiked Upscale.Caused by Noise Due to Faulty Primary Containment Penetration Connectors.Cables Rebuilt|letter dated October 17, 1986]]>
"Sus uehanna Steam Flectric Station Security Trainina And Oualification Plan" Revision A, dated Auaust 26, 1981 (by letter dated September 1,
19811 as revised by:
Pevision 8, dated February 3, 1983 (bv letters dated February 11, 1983 and October 26, 1983)
Revision C, dated January 31, 1984 (by letter dated March 12, 19841 Revision D, dated May ?8, 1985 (bv [[letter::IA-85-388, Responds to FOIA Request for Facility PRA & Related Info.Pra Not Yet Received by Nrc.Citation of Facility Data in NUREG/CR-3493.NUREG Available in PDR|letter dated June 10, 1985]])
"Sus uehanna Steam Electric Station Safequards Continqency Plan" This plan is Chapter ll of the Physical Security Plan.
AMENDMENT NO. 62 TO FACILITY OPERATING LICENSE NO. NPF SUSgUFHANNA, UNIT 1
AMENDMENT NO. 33 TO FACILITY OPERATING LICENSF NO. NPF SUS(UEHANNA, UNIT 2 DISTRIBUTION:
Docket Nos 50-387 388 NRC PDR Local PDR PRC System NSIC BMD-3 r/f MThadani (4)
EHylton (2)
EAdensam
- Attorney, OELD CMiles RDiags JPartlow BGrimes EJordan LHarmon TBarnhart (8)
FButcher