ML19310A671

Forwards Request for Addl Info Re Radiological Assessment. Info Should Be Provided by 800630

ML19310A671
Person / Time
Site:	McGuire, Mcguire
Issue date:	06/04/1980
From:	Youngblood B Office of Nuclear Reactor Regulation
To:	Parker W DUKE POWER CO.
References
NUDOCS 8006200623
Download: ML19310A671 (5)

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UNITED STATES g

g NUCLEAR REGULATORY COMMISSION g.

.p WASHINGTON, D. C. 20555

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JUN 4 B30 Docket Hos.:

50-369 and 50-370 Duke Power Company ATTN: Mr. William 0. Parker, Jr.

Vice President - Steam Production P. O. Box 33189 422 South Church Street Charlotte, North Carolina 28242

SUBJECT:

RADIOLOGICAL ASSESSMENT - REQUEST FOR ADDITIONAL INFORMATION (McGUIRE NUCLEAR STATION, UNITS 1 AND 2)

As a result of our continuing review of your application we find that we are in need of specific additional information which is described in the enclosure.

It is requested that this information be provided on or before June 30, 1980, Sincerely,

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i B. J.;Youngblood, Chief Licensing Branch No. 1 Division of Licensing

Enclosure:

Request for Additional Information-Radiological Assessment cc: See next page 80062004A3 L

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cc: fir. W. L. Porter David Flesichaker, Esq.

Duke Power Company 1735 Eye Street, N. W.

~ f P. O. Box 2178 Suite 709 422 South Church Street Washington, D. C. 20006 Charlotte, North Carolina 28242 Richard P. Wilson,.Esq.

Mr. R. S. Howard-Assistant Attorney General 4

Power Systems Division State' of South Carolina Westinghouse Electric Corporation 2600 Bull Street P. O. Box 355 Columbia, South Carolina 29201 Pittsburgh, Pennsylvania 15230 Mr. E. J. Kei th EDS "uclear Incorporated 220 Mantgonery Street San francisco, California 94104 1

' Mr. - J. E. Houghtaling NUS Corporation t

2535 Countryside Soulevard Clearwater, Florida 33515 Mr. Jesse L. Riley, President The Carolina Environnental Study Group j

854.Henley Place Charlotte, North Carolina 28207 J. Michael McGarry, III, Esq.

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Debevoise & Liberman i

1200 Seventeenth Street, N.W.

4 Washington, D. C.

20036 4

Robert M. Lazo, Esq., Chairman i

Atomic Safety and Licensing Board U. S. Nuclear' Regulatory Commission l

Washington, D. C.

20555 lDr. Enmeth A. Leubke 1

Atomic Safety.and Licensing Board U. S. Nuclear Regulatory Commission

' Washington, D. C..20555 Dr. Cadet H. Hand, Jr., Director Bodega Marine Lab of California

P. O. Box 247 4

. Sodega Bay, California 94923 s

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4 ENCLOSURE 331-1 g

331.0 RADIOLOGICAL ASSESSMEtiT 331,14 -

Provide additional information and evaluations for the effect of high (NUREG-0578, 2.1.6.b, ltr post-accident radiation levels on access and equipment operation in dtd 11/19/79 for criteria) vital areas as follows:

(12.1.1, 12.1.2, (a) Identify those areas considered vital areas for post-accident 12.1.3) recovery, considering the following areas:

control room, on-site technical control center, operational control center, security center, emergency power, supplies, radioactive waste control panels, recombiner hookup and controls, hydrogen purge controls, instrument panels, containment isolation valve reset controls, sampling stations,. ample analysis stations, manual ECCS alignment, motor control center.

State which areas will not require access under postulated pcst-accident-conditions and explain why any particular area is r,ot considered a vital area for the post-accident criteria referenced.

(12.1.6.2)

(b) Identify those systems which may contain high levels of radioactivity (12.1.2.5) and have been evaluated for effects on access to and operations in v' ital areas. Consider (as a minimum) residual heat removal, safety injection, CVCS, demineralizer, charging, RC filters, seal water filter, liquid radwaste, gaseous radwaste.

Provide an explanation for any of the above systems not evaluated or considered.

331.15 Revise and broaden your response of 1/24/80 so as to provide a description (12.3.4)

(flTOL) of the two high range containment monitors required by our letter of tiovember 9, 1979, implementing the Lessons Learned item 2.1.8.b of NUREG-0578, and specify the location of these monitors (inside containment).

The description of the monitors should include:

331-2 g

a. type of radia. tion measured; b the range or ranges of the monitors.

If two or more monitors are required to span the range in Table 2.8.1.b.3 of our Novc=ber 9,1979 letter (108 rad /hrtotalradiationork07 R/hr photons only),the ranges of the subsystem monitors must overlap (i.e., upper value/ lower f

value of overlap) by at least a factor of 10;

c. location of and type of readout (continuous and recording);

d. energy respon e (sensitive to 60 kev);

e. calibration frequency and methods (refueling frequency);

f. verification that the monitors are powered by separate vital instrument buses;

g. verification that the monitors will be oparational by 1/1,dl;

h. ve'rification that the monitors meet the seismic qualifications of Regulatory Guide 1.100 (Seismic Category I) and are environmentally qualified to survive an in-containment LOCA in accordance with Regulatory Guide 1.89.

The location of the monitors should be shown on plant layout drawings.

The monitors should be located in a manner as to provide a reasonable assessment of radiation levels inside containment. Monitors should not be placed in areas which are protected by massive shielding.

331.16 Describe the provisions which have been made to sample and analyze (NT0L)

(HUREG-0578, airborne radiciodine in vital areas as follows:

2.1.3.c; ltr 11/19/79 for

a. portable conitoring capability for radiciodine sampling; criteria)

(12.2.3.4)

b. results available within 10 minutes at a time when usage of counting /

analyses facilities is heavy;

c. controls to prevent counting system saturation from high sample activities;

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d. clean air ventilation for counting facilities to reduce analysis inaccuracies;

e. provisions for reducing background radiation levels in the analysis facility, in the sample counting device, or from the sample;

f. procedures for keeping personnel exposures ALARA during sample taking and analysis.

331.17 Your FSAR indicates that the Health Physics Supervisor may have direct (NTOL, Part 1, Item 3) access to the Station Manager in matters concerning any phase of (Fig. 13.1.2-1)

(13.1.1.2. )

radiation protection (p. 13.1-13), the station organization chart in Figure 13.1.2-1 shows the Health Physics Supervisor reporting through the Technical Services Superintendent to the Plant Manager.

Regulatory Guide 8.8, " Information Relevant to Ensuring Occupational Radiation Expos 6res at Huclear Power Stations Will be As low As is Reasonably Achievable," states that the Radiation Protection Manager (RPM),

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equivalent to your Health Physics Supervisor, should have direct recourse to the plant manager and should have direct recourse to the plant manager and should be independent of the station technical support division. The " Draft C.riteria for Utility Management and Technical Competence" specifies that the RPM should report directly to the Plant Manager.

It is our position that your Health Physics Supervisor report directly to the Station Manager and that the Station organization be revised accordingly.

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