ML20148M551

Suppl Testimony of NRC Staff in Response to Intervenor Greene County'S Stipulated Contention I.A. Re Security at Proposed Facil

ML20148M551
Person / Time
Site:	Green County
Issue date:	11/07/1978
From:	Gaitanis M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20148M544	List: ML20148M541 ML20148M546 ML20148M551 ML20148M557 ML20148M564 ML20148M577 ML20148M595 ML20148M611 ML20148M622 ML20148M632 ML20148M639 ML20148M649
References
NUDOCS 7811220062
Download: ML20148M551 (7)

Text

-. ... .. , . - .- . ._ ___ _ _ _ _ _ - _ _

O UNITED STATES OF AMERICA _

NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )

)

POWER AUTHORITY OF THE STATE Docket No. 50-549 0F NEW YORK (Greene County Nuclear Power Plant) )

SUPPLEMENTAL TESTIMONY OF NRC STAFF IN RESPONSE TO GREENE COUNTY ET AL.,

STIPULATED CONTFNTION I.A (SECURITY) by Michael J. Gaitanis

?Stieg ()o c. ,

Michael J. Gaitanis l This testimony is offered in response to Contention.I.A. of Greene 2 County et al., which reads as follows:

3 I. The Preliminary Safety Analysis Report ("PSAR") prepared I

4 by the Applicant does not provide reasonable assurance, as required 5 by 10 CFR 5550.35 and 50.40 that (a) the health and safety of the 6 public will not be endangered, and (b) the Applicant is financially )

7 qualified to engage in the proposed activities in accordance with the 8 Commission's regulations in the following respects:

9 A. The Applicant has not demonstrated that the proposed j 10 site is suitable from the point of view of complying with the 11 security requirements of Part 73 of 10 CFR due to the easy access to 12 the site from the Hudson River and the resulting exposed nature.

13 All land and water approaches to a nuclear power plant site must be 14 considered in the development of the site's physical protection systems 15 and security plan. A physical protection system for nuclear power reactors 16 is required by regulations, principally by 10 CFR Parts 50 and 73. These 17 regulations require that each applicant for a license to operate a nuclear 18 power plant provide protection to meet the general performance objectives 19 of 573.55(a) and to submit a security plan describing the equipment, 20 barriers, security organization, contingency plans, training programs and administrative controls for NRC review and approval. Applicants applying 21 f r an operating license, the receipt of which will be after February 23, 22 1979, are required to provide a physical security plan as required by 23 24 150.34(c) and to provide the level of protection identified in 573.55.

l l

1

Michael J. Gaitanis _

1 Complete implementation of the physical security plan and final 2 demonstration of compliance is required prior to issuing an operating ~l 3

license to the applicant. Satisfactory protection against intrusions 4 by land and/or water must be demonstrated in the security plan in order 5

to receive NRC approval. -l We have reviewed the information submitted by Power Authority of the 6

State of New York in its application for a construction permit describing l 7

the proposed security plan for the Greene County Nuclear Power Plant site.

8 The applicant states in the Greene County Nuclear Power Plant-PSAR 513.7.1 l 9

that "A protected area will be created by erection of a physical barrier 10 j) completely around the plant" and shows in PSAR site plan Figure 1.2-3 a continuous protected area barrier surrounding the plant. All safety 12 related structures are to be located inside the protected area. Therefore, 13 we have concluded that the applicant is planning to protect the site against g

easy cess and that there will be no unprotected access routes from the 15 Hudson River.

17 18 19 20 21 22 23 24 2

l l.

l

.o 1

.a Michael J. Gaitanis Division of Operating Reactors U. S. Nuclear Regulatory Commission ' i 1

PROFESSIONAL QUALIFICATIONS , )

l I am a Reactor Safeguards Analyst in the Reactor Safeguards Licensing Branch, Of fice of Nuclear Reactor Regulation, U. S. Nuclear Regulatory Canmission.' I am responsible for the technical aspects of safeguards 1

reviews of plant physical protection systems and plans associated wi th l licensing actions related to canmercial nuclear reactors used to generate l electric power.

I received a Bachelor of Science degree in Chemistry from the Pennsylvania State University in 1948. Industrial Management was studied at the Universi ty of Tennessee, 1955-1956, and Electronics at the Knoxville School of Electronics, 1961-1964. Other educational background includes:

1. Oak Ridge National Laboratory (prior to 1962)

a. Radiochemi stry

b. Reactor Shielding

c. Statistics

2. Short courses related specifically to safeguards at

, a. Georgia Institute of Technology - Management and Economics of Nuclear Fuels (1971)

b. Anerican Society for Industrial Security - Public utili ties Securi ty (1974)

c. Defense Industrial Security Institute - industrial Facilities Protection for Privately Owned and Privately Operated Facili ties (1975)

d. George Washington University - Introduction to Fault Free Analysis (1976) - Application of

-- Systems Analysis Methods to Security Control Programs (1976)

L m

1 a i l

. . 1

-2 From 1948 to 1951 I was employed as a chemist by Linde Air Products _

Company and Koppers Company, Inc. )

l 1

From February 1951 to August 1964 I was employ (d by Union Carbide Corp., .

l Nuclear Division at the Oak Ridge National Laboratory in a number of technical and supervisory positions. Iwasinvolvediykheanalytical )

chenistry of a number of irradiated fuel reprocessing syste s such as )

ociv.ir.r.

Purex, Thorex, and 'iolatility. I was associatec niin tr,e e rg, Level Analytical Facility, the Homogeneous Reactor (#1), the Molten Salt Reactor, the processing of plutonium and recovery of americium.

From August 1964 to July 1967 I was employed as the Plant Manager of the Quehanna Facility by the Martin Co. I was responsible for the safe, secure, and productive operation of personnel and facilities in pro-ducing radioactive fuels from Strontium-90 for thermo-electric generators.

From July 1967 to present I have been employed by the Atomic Energy Commission and the Nuclear Regulatory Commission. From 1967 to 1972 I was employed as an Isotope Fuel Specialist and then a Technical Manager by the Division of Space Nuclear Systems providing program direction j and budgetary guidance in the production of heat sources for radioisotope l

thermoelectric generators for space missions such as Apollo and Pioneer.

v v y e

• r -

.e From 1972 to 1978 I was employed as an Operations Analyst and Reactor -

Protection Specialist by the Directorate of Standards Development. l There I was responsible for recommending, administering techni, cal programs, and participating in studies directed at providing the basis for new material protection guidelines, criteria, standards and regulations. l l

In this capacity I have been the Task leader for the de,velopment and pre- l paration of the following guides for publication:

Regulatory Guide Title 1.17 Protection of Nuclear Power Plants Against Industrial Sabotage 5.10 Selection and Use of Pressure-Sensitive Seals on Containers for Onsite Storage of Special Nuclear Material 5.12 General Use of Locks in the Protection and Control of Facilities and Special Nuclear Materials 5.15 Security Seals for the Protection and Control of Special Nuclear Material In addition, I was one of four team leaders responsible for implementation of 10 CFR Part 73.50, " Requirements for physical protection of licensed activities," and 173.60, " Additional requirements for the physical protection of Special nuclear material at fixed sites." Further I was the Task Leader responsible for developing and preparing for publication in the Federal Register the regulations for the physical protection of nuclear power reactors 10 CFR Part 373.55. From May 1977 to May 1978 as a loanee from Standards Development to NRR and from May 1978 to the present as a

Reactor Safeguards Analyst, I have been the lead reviewer for physical , _

security plans submitted by eight power reactori licensees to meet the requirements of 673.55 at their sites.

9 E

a h

I l

[

t i