ML20211G743

Conformance to Reg Guide 1.97,VC Summer Nuclear Station, Informal Rept

ML20211G743
Person / Time
Site:	Summer
Issue date:	05/31/1986
From:	Stoffel J EG&G IDAHO, INC.
To:	NRC
Shared Package
ML20211G739	List: ML20211G733 ML20211G743
References
CON-FIN-A-6483, RTR-REGGD-01.097, RTR-REGGD-1.097 EGG-NTA-7231, GL-82-33, TAC-51137, NUDOCS 8606200132
Download: ML20211G743 (29)

Text

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EGG-NTA-7231 l- May 1986 INFORMAL REPORT H

CONFORMANCE TO REGULATORY GUIDE 1.97, Idaho VIRGIL C. SUMMER NUCLEAR STATION National Engineering Laboratory -

- Managed

• J. W. Stoffel by the U.S.

Department ofEnergy

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l PRELIMINARY i

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Prepared for the l n ~

+4 U. S. NUCLEAR REGULATORY COMMISSION  !

)J Wort performed under No. DE-ACO D01 10 l

8606200132 e60612 PDR ADOCK 05000395  !

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i CONFORMANCE TO REGULATORY GUIDE 1.97 VIRGIL C. SUMMER NUCLEAR STATION pa J. W. Stoffel Published May 1986 E6&G Idaho, Inc.

Idaho Falls, Idaho 83415 ,,

Prepared for the U.S. Nuclear Regulatory Commission ,

. Washington, D.C. 20555 '

1 under DOE Contract No. DE-AC07-761001570 FIN No. A6483

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ABSTRACT 1 ._

This E666 Idaho, Inc., report reviews the submittal for Regulatory Guide 1.97 for the Virgil C. Summer Nuclear Station and identifies areas of nonconformance to the regulatory guide. Exceptions to Regulatory Guide 1.97 are evaluated and those areas where sufficient basis for acceptability is not provided are identified.

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l Docket No. 50-395 TAC No. 51137 11

FOREWORD

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This report 1s supplied as part of the " Program for Evaluating Licensee / Applicant Conformance to R.G. 1.97," being conducted for the U.S.

Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of PWR Licensing-A, by ES&G Idaho, Inc., NRR and I&E Support Branch.

The U.S. Nuclear Regulatory Commission funded the work under authorization B&R 20-19-40-41-3.

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Docket No. 50-395 TAC No. 51137 iii

CONTENTS ABSTRACT .............................................................. 11 FOREWORD .............................................................. iii

1. INTRODUCTION ..................................................... 1

2. REVIEW REQUIREMENTS .............................................. 2

3. EVALUATION ....................................................... 4 3.1 Adherence to Regulatory Guide 1.97 ......................... 4 3.2 Type A Variables ........................................... 4 3.3 Exceptions to Regulatory Guide 1.97 ........................ 5 ema-

4. CONCLUSIONS ...................................................... 18 5.. REFERENCES ....................................................... 23

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- CONFORMANCE TO REGULATORY GUIDE 1.97 VIRGIL C. SUMMER NUCLEAR STATION

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1. INTRODUCTION On December 17, 1982, Generic Letter No. 82-33 (Reference 1) was issued by D. 6. Eisenhut, Director of the Division of Licensing, Nuclear l Reactor Regulation, to all licensees of operating reactors, applicants for l operating licenses and holders of construction permits. This letter  !

included additional clarification regarding Regulatory Guide 1.97, Revision 2 (Reference 2), relating to the requirements for emergency response capability. These requirements have been published as Supplement

=_ No. 1 to NUREG-0737, 'TMI Action Plan Requirements" (Reference 3).

South Carolina Electric and Gas Company, the licensee for Virgil C. Sumner Nuclear Station, provided a response to the Regulatory Guide 1.97 portion of the generic letter on April 15, 1985 (Reference 4).

This report provides an evaluation of that submittal.

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2. REVIEW REQUIREMENTS i

Section 6.2 of NVRE6-0737, Supplement No. 1, sets forth the .

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documentation to be submitted in a report to the NRC describing how the i I

licensee complies tp Regulatory Guide 1.97'as applied to emergency response

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facilities. The submittal should include documentation that provides the following information for eacht variable shown in the applicable table of i Regulatory Guide 1.97:

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1. Instrument range l

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2. Environmental qualification s

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3. Seismic qualific$ tion -

4. Quality assurance ,

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5. Redundance and sensor location l

6. Power supply j i

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7. , Location of display .

8. Schedule of installation or upgrade.

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The submittal should identify deviations from Regulatory Guide 1.97 and l provide supporting justification or alternatives. j

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Subsequent to the issuance of the generic letter..the NRC held.

regional meetings in FeDruary and March 1983, tu answer licensee and  !

applicant questions and concerns regarding the NRC policy on this subject.

At these, meeti~ngs, it was noted that the NRC review would only address r exceptions taken to Regulatory Guide 1.97. Where licensees or applicants l, explicitly state that instrument systems conform to the regulatory guide it  !

was noted that no further staff review would be necessary. Therefore, this l 2  !

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- report only addresses exceptions to Regulatory Guide 1.97. The following evaluation is an audit of the licensee's submittal based on the review

. policy described in the NRC regional meetings.

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3. EVALUATION ,

The licensee provided a response to NRC Generic Letter 82-33 on April 15, 1985; This evaluation is based on that submittal. -

3.1 Adherence to Reculatory Guide 1.97 The licensee stated that compliance with Regulatory Guide 1.97 is indicated on Table 1-1 of their submittal, which summarizes each variable's compliance with the Regulatory Guide 1.97, Revision 3 (Reference 5),

provisions. That compliance report presents justification, modifications or ongoing evaluations that are provided as resolutions for any identified deviations. .Therefore, we conclude that the licensee has provided an

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explicit commitment on conformance to Regulatory Guide 1.97. Exceptions to and deviations from the regulatory guide are noted in Section 3.3.

3.2 Tvoe A Variables Regulatory Guide 1.97 does not specifically identify Type A variables, i.e., those variables that provide the information required to permit the -

control room operator to take specific manually controlled safety actions.

-r:The licensee classifies the following instrumentation as Type A:

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1. Reactor coolant system (RCS) pressure (wide range)

2. RCS hot leg temperature (wide range)

3. RCS cold leg temperature (wide range) -

4. Steam generator level (wide range)

5. Steam generator level (narrow range)

6. Pressurizer level l

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7. Containment pressure (normal range)

8. Containment pressure (extended range)

- 9. Main steamline pressure I

10. Refueling water storage tank level j

11. Containment water level

12. Emergency feedwater flow l

13. Primary co'ntainment radiation level .

14. Core exit temperature l l

15. RCS subcooling monitor.

i The above variables meet Category 1 reconnendations consistent with the requirements for Type A variables, except as noted in Section 3.3.

'T - 3.3 Exceptions to Reaulatory Guide 1.97 The licensee identified deviations and exceptions from Regulatory Guide 1.97. These are discussed in the following paragraphs.

3.3.1 Ranae Reautrement Deviation Thelicenseeindicatesthatthefollowingvariablesconformtothh range recommended by Regulatory Guide 1.97. However, the range provided for each variable is listed as 0 to 100 percent of span. Based on this

- information we are unable to determine that the range meets the regulatory guide recommendation. .

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1. Steam generator level (wide range)

(from tube sheet to separators)

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2. Steam generator level (narrow range)

(no specific requirement) -

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3. pressurizer level (bottom to top)

4. Refueling water storage tank level (top to bottom)  :

The licensee should identify the range for each of these variables and identify and justify any deviation from the regulatory guide.

3.3.2 Control Rod Position Regulatory Guide 1.97 recommends Category 3 instrumentation with a range of full in or not full in for this variable. .

The licensee has not provided the information required by Section 6.2

. -r' of Supplement No. 1 to NUREG-0737 for this variable.

4 The licensee should provide the required information, identify any deviations from Regulatory Guide 1.97 and justify those deviations identified.

3.3.3 RCS Soluble Boron Concentration .,

Regulatory Guide T.97 recommends Category 3 instrumentation, with a range of 0,to 6000 ppe, for this variable.

The licensee has not provided the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable.

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i The licensee should provide the required information, identify any deviations from Regulatory Guide 1.97 and justify those deviations identified. . <

. 3.3.4 Core Exit Temperature The licensee has identified core exit temperature as a Type A variable. As such, it should meet Category 1 requirements. The licensee indicates that this instrumentation is Category 1 with the exception of recording.

l The NRC is reviewing the acceptability of this variable as part of their review of NUREE-0737, Item II.F.2. .

3.3.5 Coolant Inventory Regulatory Guide 1.97 recommends Category 1 instrumentation for this

- variable. The licensee has provided instrumentation that, except for redundancy, is Category 1.

The NRC is reviewing the acceptability of this variable as part of

~?'their review of NUREG-0737 Item II.F.2.

3.3.6 Dearees of Subcoolina

' The licensee has identified degrees of subcooling as a Type A variable. As such, it should meet Category 1 requirements. The licensee indicates that this instrumentation is Category 1 with the exception of redundancy.

The NRC is reviewing the acceptability of this variable as part of their review of NUREG-0737 Item II.F.2. ,

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3.3.7 Containment Pressure Regulatory Guide 1.97 reconsnends instrumentation with a range of

-5 psig to 3 times design pressure for this variable. The licensee states -

that the instrumentation provided covers a range of 0 psig to 3 times design pressure. This range does not cover the subatmospheric pressure recommended by the regulatory guide.

The licensee should expand the range monitored by the existing instrumentation to cover the entire range recommended by Regulatory Guide 1.97 or provide justification for deviating from the recommended range.

3.3.8 Containment Isolation Valve Position From the information provided, we find that the licensee deviates from  !

l a strict interpretation of the Category 1 redundancy recommendation. Only l the active valves have position indication (i.e., check valves have no . l position indication). Since redundant isolation valves are provided, we j find that redundant indication per valve is not intended by the regulatory guide. Position indication of check valves is specifically excluded by c Table 3 of Regulatory Guide 1.97. Therefore, we find that the 1 instrumentation for this variable is acceptable.

3.3.9 Radiation level in Circulatino Primary Coolant The licensee indicates that radiation level measurements to indicate fuel cladding failure are provided by the post-accident sampling system,

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which is being reviewed by the NRC as part of their review of NUREG-0737, l Item II.B.3.

l Based'on the alternate instrumentation provided by the licensee, we l conclude that the instrumentation supplied for this variable is adequate I

and, therefore, acceptable.

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3.3.10 Condenser Air Removal System Exhaust--Noble Gas and Vent Flow Rate The licensee has not provided the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable. ,

The licensee should provide the required information, identify any deviations from Regulatory Guide 1.97 and justify those deviations identified.

3.3.11 Effluent Radioactivity--Noble Gases (from buildinas or areas--) .

The licensee has not provided the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable.

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-_ . 1 The license's should provide the required information, identify any deviation from Regulatory Guide 1.97 and justify those deviations identified.

i 3.3.12 Residual Heat Removal (RHR) Heat Exchanaer Outlet Temperature Regulatory Guide 1.97, Revision 3, recommends a range of 40 to 350'F for this variable. The licensee has provided a range of 50 to 400*F.

-ri This deviation is less than three percent of the auximum recommended l range. Considering instrument accuracy and overall range, we consider this deviation minor and, therefore, acceptable. f l

3.3.13 Accumulator Tank Level and Pressure ,

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The licensee has not provided the information required by Section 6.2  !

of Supplement No. 1 to NUREG-0737 for these variables.

The licensee should provide the required information, identify any  ;

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deviations from Regulatory Guide 1.97 and justify those deviations  !

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3.3.14 Accumulator Isolation Valve Position

. The licensee has not provided the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for these variables. ,

The licensee should provide the required information, identify any deviations from Regulatory Guide 1.97 and justify those deviations identified.

3.3.15 toric Acid Charoina Flow The Itcensee has not provided the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable.

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-- -The licensee should provide the required information, identify any deviations fron Regulatory Guide 1.97 and justify those deviations identified.

l 3.3.16 Flow in Hiah Pressure Injection (HPI) System Regulatory Guide 1.97 recommends a range of 0 to 110 percent design flow for this variable. The licensee has provided a range of 0 to

'I' 100 percent of design flow.

The licensee has not provided justification for this deviation. The i licensee should submit the basis that shows that this instrumentation range will cover any expected flow, or provide the range recommended by Regulatory . Guide 1.97.

3.3.17 Reactor Coolant Pumo Status  ;

The 1.icensee has not provided the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable.

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l The licensee should provide the required information, identify any deviations from Regulatory Guide 1.97 and justify those deviations identified. . .

. 3.3.18 Pressurizer Heater Status Regulatory Guide 1.97 recommends monitoring the pressurizer heater electric current with Category 2 instrumentation. The licensee has provided electric current instrumentation that, except for environmental qualification, is Category 2.

1 Environmental qualification has been clarified by the Environmental .

- Qualificatio'n Rule,10 CFR 50.49. The licensee should therefore provide ,

the required justification for this deviation from Regulatory Guide 1.97 or provide instrumentation that is environmentally qualified in accordance with the provisions of 10 CFR 50.49 and Regulatory Guide 1.97. )

I 3.3.19 Ouench Tank Level )

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The licensee has not provided the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable.

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The licensee should provide the required information, identify any '

deviations from Regulatory Guide 1.97 and justify those deviations j identified. l l

3.3.20 Ouench Tank Temperature l The licensee has not provided the information required by Section 6.2 i of Supplement No. 1 to NUREG-0737 for this variable.

The licensee should provide the required information, identify any deviations from Regulatory Guide 1.97 and justify those deviations l identified.

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3.3.21 Ouinch Tank Pressure i

The licensee has not provided the information required by Section 6.2 ,

of Supplement No. 1 to NUREG-0737 for this variable. ,

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The licensee should provide the required information, identify any deviations from Regulatory Guide 1.97 and justify those deviations identified.

3.3.22 Steam Generator Pressure Regulatory Guide 1.97 recommends instrumentation for this variable with a range from atmospheric pressure to 20 percent above the lowest

_ safety valve setting. The licensee states that their instrument range is 0 to 100 percent pressure.

Based on this information, we are unable to determine that the provided range is adequate. The licensee should provide information on the .

lowest and highest safety valve setpoints and the range of pressure the instrument monitors.

3.3.23 Heat Removal by the Containment Fan Heat Removal System

The licensee has not provided the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable.

The licensee should provide the required information, identify any deviations from Regulatory Guide 1.97 and justify those deviations identified. --

3.3.24 Containment Atmosphere Temperature The licensee has not provided the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable.

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The licensee should provide the required information, identify any deviations from Regulatory Guide 1.97 and justify those deviations identified. .

. 3.3.25 Containment Sumo Water Temperature l

The licensee has not provided the information requ1 red by Section 6.2 l of Supplement No. I to NUREG-0737 for this variable.

The licensee should provide the required information, identify any deviations from Regulatory Guide 1.97 and justify those deviations identified.

3.3.26 Hich-Level Radioactive Liouid Tank Level The licensee has not provided the information required by Section 6.2

! of Supplement No. 1 to NUREG-0737 for this variable.

The licensee should provide the required information, identify any deviations from Regulatory Guide 1.97 and justify those deviations identified.

3.3.27 Radioactive Gas Holduo Tank Pressure The licensee has not provided the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable.

The licensee should provide the required information, identify any deviations from Regulatory Guide 1.97 and justify those deviations

, identified.

- 3.3.28 Emeraency Ventilation Damper Position

} The licensee has not provided the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this tariable.

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The licensco sh:uld prsvide the required infermatien, idIntify any l deviations from Regulatory Guide 1.97 and justify those deviations l identified. . ,

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3.3.29 Radiation Exposure Rate . ,

Regulatory Guide 1.97 recommends instrumentation with a range of

! 10 to 10 R/hr for this variable. The licensee has provided instrumentation with ranges from 10 to 10 R/hr. The licensee states that the existing area monitors must be augmented by high range portable survey instrumentation to meet the range requirements.

From a radiological standpoint, if the radiation levels reach or

. exceed the upper limit of the range, personnel would not be permitted into

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the areas without additional monitoring with portable monitors. Based on i i

the alternate instrumentation used by the licensee for this variable, we find the proposed ranges for the radiation exposure rate monitors acceptable. .

3.3.30 Containment or Purae Effluent--Noble Gases

Regulatory Guide 1.97 recommends a range of 10' to 10' pCi/cc P- for this variable. The licensee has provided a range that does not meet the recommended minimum sensitivity. The licensee provided a minimum range

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of 2 x 10 pC1/cc.

' We find this small deviation from the range recommendation to be acceptable for this variable. The range provided will adequately monitor j the coeration of this system during accident and post-accident conditions.

Therefore, this is an acceptable deviation from Regulatory Guide 1.97.

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3.3.31 Vent From Steam Generator Relief Valves or Atmospheric Oumo Valves i

! The licensee has not provided the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable, i

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The licensee should provide the required information, identify any deviations from Regulatory Guide 1.97 and justify those deviations l identified. ,

. 3.3.32 Airborne Radiohalonens and Particulates The licensee has not provided the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable.

The licensee should provide the required information, identify any deviations from Regulatory Guide 1.97 and justify those deviations identified.

3.3.33 Plant and Environs Radiation (nortable instrumentation)

Regulatory Guide 1.97 recommends ranges for this variable of 10~ to

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10 R/hr, photons and 10 to 10* rads /hr, beta radiation and low-energy photons. The licensee states that the ranges provided for this variable are 1 to 100 mR/hr and 10~ to 10 R/hr. No justification was submitted for this deviation.

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3.3.34 Plant and Environs Radioactivity (nortable instrumentation)

The licensee has not provided the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable.

The licensee should provide the required information, identify any deviations from Regulatory Guide 1.97 and justify those deviations identified.

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3.3.35 Wind Direction The licensee has not provided the instrument range information required by Section 6.2 of Supplement No. I to NURE6-0737 for this variablet

, The licensee should provide the required information, identify any deviation from Regulatory Guide 1.97 and justify those deviations identified.

3.3.36 Wind Soeed The itcensee tas not provided the instrument range information required by Section 6.2 of Supplement No. 1 to NURE6-0737 for this variable.

The licensee should provide the required information, identify any deviation from Regulatory Guide 1.97 and justify those deviations identified.

3.3.37 Estimation of Atmosoheric Stability The licensee has not provided the instrument range information

- required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable.

The licensee should provide the required information, identify any I deviation from Regulatory Guide 1.97 and justify those deviations j identified.

i' 3.3.38 Primary Coolant and Sumo Samplina Canabilitv j The licensee has not provided the instrument range information

required by Section 6.2 of Supplement No. I to NURE6-0737 for this variable, i

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-- . . , - - , - , . , - - - , _ , - , - - - - - - . - - . , , , - , , _ , - - - . - . - . . - - - _ _ , , - .-,-,._,...-,..,.--._n,. -. -.,.--nn---,------,,--r,.n , ,- .,-

i The licensee should provide the required information, identify any deviations from Regulatory Guide 1.97 and justify those deviations identified. .

. 3.3.39 Containment Air Samplina Caoability The licensee has not provided the instrument range information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable.

The licensee should provide the required information, identify any deviations from Regulatory Guide 1.97 and justify those deviations identified.

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i 4. CONCLUSIONS Based on our review, we find that the licensee either conforms to or is justified in deviating from Regulatory Guide 1.97, with the following

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j exceptions: .

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1. Range requirement deviation--the licensee should provide the range monitored for the four variables listed and justify any  !

deviation from the regulatory guide (Section 3.3.1). l 1

2. Control rod position--the licensee should provide tha information

! required by Section 6.2 of Supplement No. 1 to NUREG-0737 for

. this variable, identify any deviations and justify those deviations identified (Section 3.3.2).

3. RCS soluble boron concentration--the licensee should provide the information required by Section 6.2 of Supplement No. 1 to i NUREG-0737 for this variable, identify any deviations and' justify -

l those deviations identified (Section 3.3.3).

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j 4. Containment pressure--the licer ut should expand the existing e range for this variable or just1fy the use of the existing range

!' (Section 3.3.7).

5. Condenser air removal system exhaust--the licensee should provide the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable, identify any deviations and justify thosedeviationsidentified(Section3.3.10).

6. Effluent radioactivity, noble gases--the licensee should provide the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable, identify any deviations and justify those deviations identified (Section 3.3.11). ,

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7. Accumulator tan': level and pressure--the licensee should provide j the information required by Section 6.2 of Supplement No. 1 to )

NUREG-0737 for this variable, identify any deviations and justify

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, those deviations identified (Section 3.3.13). ,

8. Accumulator isolation valve position--the licensee should provide j the information required by Section 6.2 of Supplement No. 1 to {

NUREG-0737 for this variable, identify any deviations and justify l i

those deviations identified (Section 3.3.14).

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9. Boric acid charging flow-the licensee should provide the i f information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable, identify any deviations and justify l

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1 those 1 deviations identified (Section 3.3.15).

l' l 10. Flow in high pressure injection (HPI) system--the licensee should provide the range recommended by Regulatory Guide 1.97 for this o variable or justify the existing range (Section 3.3.16). l

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j 11. Reactor coolant pump status--the licensee should provide the j i information required by Section 6.2 of Supplement No. 1 to l

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NUREG-0737 for this variable, identify any deviations and justify those deviations identified (Section 3.3.17). I

12. Pressurizer heater status--the licensee should provide environmentally qualified instrumentation for this variable or justify the lack of it (Section 3.3.18). l

13. Quench tank level--the licensee should provide the information {

required by Section 6.2 of Supplement No. 1 to NUREG-0737 for

.this variable, identify any deviations and justify those  ;

deviations identified (Section 3.3.19).  !

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14. Quench tank temperature--the licensee should provide the 4

. information required by Section 6.2 of Supplement No. 1 to NURE6-0737 for this variable, identify any deviations and justify

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, those deviations identified (Section 3.3.20).

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15. Quench tank pressure--the licensee should provide the information i required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable, identify any deviations and justify those deviations identified (Section 3.3.21).

16. Steam generator pressure--the licensee should provide the range monitored by this instrumentation and the highest and lowest l . safety valve settings (Section 3.3.22). l

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17. Heat removal by the containment fan heat removal system--the 4

licensee should provide the information required by Section 6.2 i

j of Supplement No. 1 to NURE6-0737 for this variable, identify any J l deviations and justify those deviations identified .

j (Section 3.3.23).

18. Containment atmosphere temperature--the licensee should provide

, e the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable, identify any deviations and justify I

those deviations identified (Section 3.3.24).

19. Containment sump water temperature--the licensee should provide 4 the information required by Section 6.2 of Supplement No. 1 to

! NUREG-0737 for this variable, identify any deviations and justify ,

those deviations identified (Section 3.3.25).

20. High level radioactive liquid tank level--the licensee should l provide the information required by Section 6.2 of Supplement l No. 1 to NURE6-0737 for this variable, identify any deviations and justify those deviations identified (Section 3.3.26).

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k l, 21. Radioactive gas holdup tank pressure--the licensee should provide the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable, identify any deviations and justify those deviations identified (Section 3.3.27).

22. Emergency ventilation damper position--the licensee should provide the information required by Section 6.2 of Supplement No. 1 to NURE6-0737 for this variable, identify any deviations and justify those deviations identified (Section 3.3.28).

23. Vent from steam generator safety relief valves or atmospheric dump valves--the licensee should provide the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable, identify any deviations and justify those deviations -

identified (Section 3.3.31).

24. Airborne radiohalogens and particulates--the licensee should

- provide the information required by Section 6.2 of Supplement

! No. I to NURE6-0737 for this variable, identify any deviations and justify those deviations identified (Section 3.3.32).

!- -n 2 5 .' Plant and environs radiation (portable instrumentation)--the licensee should provide the ranges recommended by Regulatory l Guide 1.97 or justify the use of the existing ranges (Section 3.3.33).

26. Plant and environs radioactivity--the licensee should provide the information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable, identify any deviations and justify those deviations identified (Section 3.3.34).

- 27. Wind direction--the licensee should provide the instrument range l

information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable, identify any deviation and justify those deviations identified (Section 3.3.35).

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28. Wind sperd--tha lic:::see should provid) the instrument range informattor, required by.Section 6.2 of Supplement No. 1 to

. NUREG-0737 for this variable, identify any deviation and justify j those deviations identified (Section 3.3.36). ,

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29. Estimation of atmospheric stability--the licensee should provide the instrument range information required by Section 6.2 of Supplement No. 1 to NURE6-0737 for this variable, identify any ,

deviation and justify those deviations identified (Section 3.3.37).  ;

30. Primary coolant and sump sampling capability--the licensee should provide the instrument range information required by Section 6.2

- of Supplement No. 1 to NURE6-0737 for this variable, identify any deviations and justify those deviations identified (Section 3.3.38). i k

31. Containment air sampling capability--the licensee should provide .

j the instrument range information required by Section 6.2 of l

Supplement No. 1 to NURE6-0737 for this variable, identify any deviations and justify those deviations identified l

(Section 3.3.39).

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5. REFERENCES 4'

1. NRC letter, D. 6. Eisenhut to All Licensees of Operating Reactors, Applicants for Operating Licenses, and Holders of Construction

. Permits, " Supplement No. 1 to NUREG-0737--Requirements for Emergency ~

Response tapability (Generic Letter No. 82-33)," December 17, 1983.

2. Instrumentation for Licht-Water-Cooled Nuclodir Power Plants to Assess Plant and Environn Conditions Durina and Fo' owina an Ace' dent, Regulatory Guide l.97, Revision 2, NRC, Office of Standards Development, December 1980.

3. Clarification of TNI Action Plan Reauirements. Recuirementu for Emeroency Response Capabi' ity, NUREG-0737, Supplement No. , NRC, Office of Nuclear Reactor Regulation, January 1983.

4. South Carolina Electric and Gas Company letter O. W. Dixon, Jr. to H. Denton, NRC, April 15, 1985.

- 5. Instrumentation for Lich<;-Water-cooled Nuclear Power Plants to Assess Plant and Environs Condi<; ions Durina and Fo' owine an Accident,

! Regulatory Guide 1.97 Revision 3 NRC, Office of Nuclear Regulatory Research, May 1983.

a 4- e 38144 l

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1. 848UOGRAPHIC DATA SHEET EGG-NTA-7231

. firk. .a.o .w.t.7 63 3 L..w. 6 es Conformance to Regulatory Guide 1.97,

. Virgil C. Sumer Nuclear Station

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May 1986

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i EGSG Idaho Inc. , , , , , , , , , , , , , , , ,

Idaho Falls, ID 83415 A6493 i.-- - u on . vie w . ue ... rw. o. wt Division of PWR Licensing - A Preliminary Technical Office of Nuclear Reactor Regulation Evaluation Report

U. S. Nuclear Regulatory Commission . a.a*oca ea u - '

Washington, DC 20555 --

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This EG&G Idaho, Inc. report reviews the submittal for the Virgil C. Sumer

, , Nuclear Station, and identifies areas of nonconformance to Regulatory Guide 1.97.

Exceptions to these guidelines are evaluated and those areas where sufficient i basis for acceptability is not provided are identified.

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