ML20138R555

Forwards Emergency Response Facility Appraisal Repts 50-369/85-29 & 50-370/85-28 on 850903-11.No Violations or Deviations Noted.Lists of Weaknesses,Open Items & Improvement Items Encl.Response Requested within 45 Days

ML20138R555
Person / Time
Site:	Mcguire, McGuire
Issue date:	12/23/1985
From:	Brownlee V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Tucker H DUKE POWER CO.
Shared Package
ML20138R556	List: ML20138R555 ML20138R561
References
RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8512310363
Download: ML20138R555 (7)

See also: IR 05000369/1985029

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DEC 2 31985  :

/ Duke Power Company

ATTN: Mr. H. B. Tucker, Vice President

Nuclear Production Department

422 South Church Street

Charlotte, NC 28242

Gentlemen:

SUBJECT: MCGUIRE EMERGENCY RESPONSE FACILITY APPRAISAL

The NRC-is conducting special appraisals of emergency response facilities (ERFs)

at all operating nuclear power reactors to verify that licensees have completed

these facilities and have met ti respective requirements defined in Supplement 1

to NUREG-0737. The objectives of these appraisals are to determine that the ERFs

are capable of performing those functions needed to assist licensees in taking

adequate protective measures in the event of a radiological emergency, and to

assure that requirements in Supplement 1 to NUREG-0737 have been satisfied. We

will use the findings from these appraisals as a basis not only for requesting

individual licensee action to correct deficiencies, but also for effecting

improvements in NRC requirements and guidance.

During the period of September 3-11, 1985, the NRC conducted a special appraisal

of the .ERFs at the McGuire Nuclear Station. This appraisal was performed using

Draft Revision 5 of IE Inspection Procedure 82212. Areas examined during this

appraisal are identified in the. enclosed report (50-369/85-29, 50-370/85-28).

Within these areas, the appraisal team reviewed selected procedures and records,

inspected the facil'. ties, equipment and supplies, observed simulated use of the

equipment and supplies, and interviewed personnel.

Within the scope of this appraisal, no violations or deviations were identified.

The findings of this appraisal indicate that certain weaknesses exist. These are

discussed in Appendix A, Appraisal Weaknesses. The appraisal also indicates that

several areas were found to be incomplete, and could not be evaluated during the

appraisal. These findings are listed in. Appendix B, Appraisal Open Items.

Finally, there are areas ~ which should be evaluated and considered for

improvement. These areas are listed in Appendix C, Appraisal Improvement Items.

We recognize that explicit regulatory requirements pertaining to improvement

items may not currently exist. Notwithstanding the latter, please advise us

within 45 days of the date of this letter of action you plan _to take, showing the

estimated date of completion with regard to the findings identified in the

Appendices.

With regard to the Appraisal open items, we are particularly interested in-your

proposed reconfiguration of the McGuire Technical -Support Center (TSC) and m

completion for construction of your Crisis Management Center (CMC). Your

continued progress regarding these facilities will be reviewed in future

inspections.

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I In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosures will l

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be placed in the NRC Public Document Room, unless you notify this office, by

telephone, within ten days of the date of this letter and submit written

application to withhold information contained therein within thirty days of the

date of this letter. Such application must be consistent with the requirements

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of 2.790(b)(1). If we do not hear from you in this regard within the specified

periods roted above, the report will be placed in the Public Document Room.

Should you have any questions concerning this letter, please contact us.

j Sincerely,

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j Virgil L. Brownlee, Chief

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Reactor Projects Branch 2

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Division of Reactor Projects

Enclosures:

} 1. Appendix A, ERF Weaknesses

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2. Appendix B, ERF Open Items

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3. Appendix C, ERF Improvement

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! 4. Inspection Report Nos.:

50-369/85-29 and 50-370/85-28

g,c w/encls:

v'T. L. McConnell, Station Manager

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State of South Carolina

Document Control Desk

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APPENDIX A

APPRAISAL WEAKNESSES

The following items indicated areas of weakness in the Emergency Response

Program:

1. Meteorological data processed through the Operator Aid Computer had not been

validated (1.2.4.2). (50-369/85-29-17,50-370/85-28-17)

2. There was no procedure for use of the OAC for calculating dose assessment

(1.2.4.2). (50-369/85-29-25,50-370/85-28-25)

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APPENDIX B

APPRAISAL OPEN ITEMS

The following items were incomplete and will be reviewed in future inspections:

1. Definition of the ' xtent

e of planned spatial and configuration changes to the

Technical Support Center and projected completion of same (1.1.1.1).

(50-369/85-29-01, 50-370/85-28-01)

2. Implementation of Regulatory Guide 1.97, monitoring with any exceptions

confirmed by NRR (1.2.1.3). (50-369/85-29-13,50-370/85-28-13)

3. Submittal to NRC of complete documentation (description of the technical

basis) for the puff-advection atmospheric dispersion model and a complete

description of the upgraded meteorological measurements program (1.2.4.2).

(50-369/85-29-21, 50-370/85-28 1)

4 Submittal to NRC of anpropriate documentation required to complete

evaluation of the Class A Model computerized dose assessment (1.2.4.2).

(50-369/85-29-23, 50-370/85-28-23)

5. Completioa of construction and establishment of ooerational readiness of the

consoiidated Crisis Management Center. (3.1.1.2). (50-369/85-29-33,

50-370/85-28-33)

6. Establishment of dedicated communication lines between the CMC and VAX

computers, and use of dial-up as backup (3.2.3). (50-369/85-29-36,

50-370/85-28-36)

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APPENDiv C

APPRAISAL IMPROVEMENT ITEMS

The following items should be evaluated and considered far improvement:

1. Expansion of the Technical Support Center (TSC) dose assessment. area to

approximately three times its present size or approximately 300 souare feet

to accommodate the expected staff (1.1.1.1). (IFI 50-369/85-29-02,

50-370/85-28-02)

2. Sizing the Emergency Director's of fice - Room 913, to accommodate the

personnel expected to staff the general area (1.1.1.1).

-(IFI 50-360/85-29-03, 50-370/85-28-03)

3. Increasing the computer room by approximately two feet to provide additional

walking and maintenance space. (1.1.1.1).

(IFI 50-369/85-29-04, 50-370/85-28-04)

4. Providing areas of the TSC with acditional writing surfaces, dccument

lay-down areas, and chairs (1.1.1.1). (IFI 50-369/85-25-05,

50-370/85-24-05)

5. Main _taining radiation monitors in the TSC in an operating mode on a

continuous basis (1.1.1.5). (IFI 50-369/85-29-06, 50-370/85-28-06)

6. Using a different technique to alert control room operators that core

temperature is outsice of the expected range (1.1.1.6).

(IFI 50-369/85-29-07. 50-370/85-28-07)

7. Validating Goerator Aid Computer (OAC) data through 'use of appropriate

software algorithms. (1.1.1.6). (IFI 50-369/85-29-08, 50-370/85-28-08)

8. Automating the presen manual transfer of cata from the OAC to VAX

computers, providing tne VAX with continuous access to data, at or near

real-time (1.1.1.6). (IFI 50-369/85-29-09, 50-370/85-28-09)

9. Providing graphic trending capability in the TSC using a sampling frequency

of _ trended data adequate to detect -significant changes (1.1.1.6). (IFI

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50-369/85-29-10, 50-370/85-28-10)

10. Changing the OAC terminal keyboards,

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positioned in a nearly vertical

orientation, to an ergonomically correct position to minimize mis-keying

(1.1.1.6). (IFI-50-369/85-29-11, 50-370/85-28-11)

11. Providing procedures or instructions developed to describe tne method for

obtaining monitoring data from the OAC - in the TSC (1.1.2.1). (IFI

50-369/85-29-12,50-370/85-28-12)

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Appendix C 2

12. Acquiring a dedicated line if trend plotting will be relied on to support

critical plant safety analysis (1.2.3.3). (IFI 50-369/85-29-14,

50-370/85-28-14)

13. Evaluating locations of the meteorological towers to determine the quality

of data, and the effects of the nearby warehouse buildings, proximity of

major plant structures. and uneven terrain in ' the area on such data

(1.2.4 2). (IFI 50-369/85-23-15, 50-370/85-28-15)

14. Incorporating the meteorological measurements program, as updated in 1983,

into the FSAR (1.2.4.2). (IFI-50-369/85-29-16, 50-370/85-28-16).

15. Evaluating the representativeness of meteorological data from the National

Weather Service (NWS) station at Charlotte and/or Catawba for real-time

conditions at McGuire or installating of backup or redundant onsite

meteorological measurements, including separate power supolies, cabling, and

recorders (1.2.4.2). (IFI 50-369/85-29-18, 50-370/85-28-18)

16. Revising procedures which provide for use of meteorological data to reflect

the hierarchy for data substitution, and specifying averaging period (e.g.,

15 minutes) and valid time of the observations (1.2.4.2).

(IFI 50-369/85-29-19, 50-370/85-28-19)

17. Specifying averaging period and valid time of observation for digital

displays of meteorological cata (e.g., via the OAC or the summary sheet

provided through the VAX computer) (1.2.4.2). (IFI 50-369/85-29-20,

50-370/85-28-20)

18. Identifying of regional and forecast n'eteorological information to be

provided on reouest by the NWS 5tation in Charlotte (1.2.4.2.).

(IFI 50-369/85-29-22, 50-370/85-28-22)

19. Modifying the Dose Assessment Class A Model to include ingestion pathway ,

dose calculations and making available to the NRC or submitting to the NRC l

documentation related thereto. (1.2.4.2.B). (IFI 50-229/85-29-24, I

50-370/85-28-24).

20. Evaluating the Nuclear-23 method to assure that both whole body and thyroid

doses are appropriately considered in protective action recommendations

(1.2.4.2.8). (IFI 50-369/85-29-26, 50-370/85-28-26)

21. Making the " Nuclear-23" available for periodic use during exercises to

assure control room personnel proficiency in use of the program. Licensee

representatives stated that use of " Nuclear-23" is prevented by interlock or

relay until such time that an emergency occurs (1.2.4.2.B).

(IFI 50-369/85-29-27, 50-370/85-28-27)

22. Providing an uninterrupted power supply for all necessary components of the

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data acquisition and display system, e.g., the VAX computer, the dose

assessment terminal, the Mohawk data link, etc. (1.2.6.2). (IFI

50-369/85-29-28, 50-370/85-28-28)

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Appendix C 3

23. Verifying that the Crisis Management Center (CMC) does not exercise priority

to the VAX thus requiring the Station to conduct manual calculation of dose

assessments. (1.2.7.1). (IFI 50-369/85-29-29, 50-370/85-28-29)

24. Inserting into procedures the actual levels at which emergency action is

required for event classification in lieu of referencing " Exceeds Technical

Specifications" or " Exceeds 10 x Tech Specs" (1.2.7.2). (IFI

50-369/85-29-30, 50-370/85-28-30)

25. Providing emergency lighting in the OSC (2.1.1.3) . (IFI 50-369/85-29-31,

50-370/85-28-31)

26. Improving the quality of drawings to include phone locations, phone numbers,

air supply headers, etc. (2.1.1.4). (IFI 50-369/85-29-32, 50-370/85-28-32)

27. Providing site emergency planning zone maps for the McGuire Station

(3.1.1.6). (IFI 50-369/85-29-34, 50-370/85-28-34)

28. Providing the CMC with a continuous data stream at, or near, real time

(3.1.1.6). (IFI 50-369/85-29-35, 50-370/85-28-35)

29. Standaroi:ing McGuire Station data sets to include all Regulatory Guide 1.97

parameters in the standard format (3.7.2). (IFI 50-369/85-29-37,

50-370/85-28 37)

20. Improving the method of data transmission to the CMC such that data is

real-time, or near real-time data (3.7.2). (IFI 50-369/85-29-38,

50-370/85-29-38)

31. Reviewing Enclosure 5.5 to procedure HP/0/B/1009/13 regarding source term-

" corresponds to" to ensure that its intended purpose is understood

(3.3.3.3). (IFI 50-369/85-29-39, 50-370/85-28-39)

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