ML19246B075

Forwards Category 2 & 3 Regulatory Positions to Be Addressed in Sep.Reg Guide 1.114 Encl

ML19246B075
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	06/11/1979
From:	Ziemann D Office of Nuclear Reactor Regulation
To:	Linder F DAIRYLAND POWER COOPERATIVE
References
TASK-***, TASK-RR NUDOCS 7907110647
Download: ML19246B075 (7)

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UNITED STATES 8

h NUCLEAR REGULATORY COMMISSION

-C W ASHINGTON, D. C. 20555 ti

'l gv j June 11,1979 Docket No. 50-409 Mr. Frank Linder General Manager Dairyland Power Cooperative 2615 East Avenue South La Crosse, Wisconsin 54601

Dear Mr. Linder:

RE:

IMPLEMENTATION 0F CATEGORY 2 AND 3 REGULATORY GUIDES IN THE SYSTEMATIC EVALUATION PROGRAM - LA CROSSE BOILING WATER REACTOR In the Systematic Evaluation Program for your facility we plan to address Regulatory Guides and other staff positions that have been classified as Category 2 or 3 for implementation by our Regulatory Requirements Review Committee.

Category 2 and Category 3 are defined as follows:

Category 2:

Further staff consideration of the need for backfitting appears to be required for certain identified items of the regulatory position - these individual issues are such that existing plants need to be evaluated to determine their status with regard to these safety issues to determine the need for backfitting.

Category 3: Clearly backfit.

Existing plants should be evaluated to determine whether identified items of the regulatory position are resolved in accordance with the guide or by some equivalent alternative.

For your information, a list of the Category 2 and 3 positions that we currently plan to address is provided in Enclosure 1.

The SEP topics under which these issues will be considered is also shown.

A copy of one Category 3 position, Regulatory Guide 1.114, Revision 1, " Guidance on Being Operator at the Controls of a Puclear Power Plant", is provided in.

To complete our evaluation of this specific guice you are requested to provide a commitment to meet the recommendations of the guide.

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7 0071_g g gy,

Mr. Frank Linder

-2' June 11,1979 Please contact the assigned Project Manager for your facility if you have any questions or comments about these matters.

Sincerely,

$4wwa-m hw Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors

Enclosures:

1.

List of Category 2 and 3 Positions 2.

Regulatory Guide 1.114 cc w/ enclosures:

See next page C,()

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Mr. Frank Linder June 11,1979 cc w/ enclosures:

Fritz Schubert, Esquire Staff Attorney Dairyland Power Cooperative 2615 East Avenue South La Crosse, Wisconsin,54601

0. S. Heistand, Jr., Esquire Morgan, Lewis & Bockius 1800 M Street, N. W.

Washi ngton, D. C.

20036 Mr. R. E. Shimshak La Crosse Boiling Water Reactor Dairyland Power Cooperative P. O. Box 135 Genoa, Wisconsin 54632 Coulee Region Energy Coalition ATTN:

George R. Nygaard P. O. Box 1583 La Crosse, Wisconsin 54601 La Crosse Public Library 800 Main Street La Crosse, Wisconsin 54601 K M C, Inc.

ATTN:

Richard E. Schaffstall 1747 Pennsylvania Avenue, N. W.

Suite 1050 Washington, D. C.

20006

a ENCLOSURE 1 CATEGORY 2 AND 3 MATTERS TO BE ADDRESSED IN THE SEP CATEGORY 2 MATTERS Codument Nunter Revision Date Title Topic RG 1.27 2

1/76 Ultimate Heat Sink for Nuclear II-3.C Power Plants RG 1.52 1

7/76 Design, Testing, and Maintenance VI-8 Criteria for Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light Water Cooled Nuclear Power Plants (Revision 2 has been published but the changes from Revision.1 to Revision 2 tr.sy, but need not, be considered.

RG 1.59 2

8/77 Design Basis Floods for Nuclear II-3.8

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Power Plants RG 1.63 2

7/78 Electric Penetration Assemblies in III-12 Contain. ment Structures for Light Water Cooled Nuclear Power Plants RG 1.91 1

2/78 Evaluation of Explosioni Postulated II.l.C to Occur on Transportation Routes Hear Nuclear Power Plant Sites RG 1.102 1

9/76 Flood Protection for Nuclear Power II-3.B Plants l

RG 1.108 1

8/77 Periodic Testing of Diesel VIII.2 i'

Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants RG 1.115 1

7/77 Protection Against Low-Trajectory III-4.B Turbine Missiles l

RG 1.117 1

4/78 Tornado Design Classification III-4.A RG 1.124 1

1/78 Service Limits and Leading III-9 Combination: for Class 1 111-11 Linear Type Component Supports III-9 RG 1.130 0

7/77 Design Limits and Loading Combinations for Class 1 Plate-and Shell-Type 111-11 Component Supports (Continued)

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CATEGORY 2 MATTERS (CONT'D)

Continued Document Nurte r Revision Date Title Tooie a

1/78 Fuel Oil Systees for Standby VIII-2 RG 1.137 0

Diesel Generators (Paragraph C.2)

BTP ASB Guidelines for Fire Protection for IX-6 9.5-1 1

Nuclear Power Plants (See Itplementation Section, Section D) 5TP HTEB 5-7 4/77 Material Selection and Processing V-4 Guidelines for BWR Coolant Pressure Boundary Piping RG 1.141 0

4/78 Contain ent Isolation Provisions VI-4 for Fluid Systems 9

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.. CATEGORY 3 MATTERS Document Mu-6 e r Revision Date Title Topic RG 1.99 1

4/77 Effects of Residual Elements on V-6 Predicted Radiation Damage to Reactor Yessel Materials (Paragraphs C.1 and C.2.

RG 1.101 1

3/77 Emergency Planning for Nuclear XIII-l Power Plants RG 1.114 1

11/76 Guidance on Being Operator at the ORB f2 Controls of a Nuclear Power Plant RG 1.121 0

8/76 Bases for Plugging Degraded PWR V-8 Steam Generator Tubes RG 1.127 1

3/78 Inspection of Water-Control Structures III-3.C Associated with Nuclear Power Plants RSS 5-1 l

1/78 Branch Technical Position: Design Require VII-3 ments of the Residual Heat Receval System V-II.B RSB 5-2 0

3/78 Branch Technical Position: Reactor V-S Coolant System Overpressurization Protection RG 1.97 1

8/77 Instrumentation for Light Water VII-5 Cooled Nuclear Power Plants to I

Assess Plant Conditions During and Following an Accident (Paragraph C.3 - with additional guidance on paragraph C.3.d to beprovidedlater)

RG 1.56 1

7/78 Maintenance of Water Purity in V-12. A Boiling Water Reactors

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. MATTERS THAT ARE NOT TO BE ADDRESSED, 1.

Re9ulatory Guide 1.105 " Instrument Setpoints" - This matter was included ir. the SEP Topic VII-1.B and was resolved on the basis of the NUREG-0138 discussion of the topic.

However, DDR generic action on specific instrumentation such as LPRM drif t in BWRs is continuing (such action was noted in the NUREG) and these generic reviews may be expanded if the need to do so is identified.

2.

Regulatory Guide 8.8 "Information Reievant to Ensuring That Occupational Radiation Exposure at Nuclear Power Stations Will Be As Low As is Reasonably Achievable (Nuclear Power Reactors)" -

This matter is presently being proposed for resolution by COR/EEB on a generic basis.

Since ALARA issues were not included in the initial SEP scope it would be inappropriate to include this one unique issue now.

3.

Regulatory f,uide 1.68.2 " Initial Startup Test Program to Demonstratt Remote Shutdown Capability for Water-Cooled Nuclear Power Plants" -- This matter was determined, by Regulatory Requirements Review Comittee, to be applicable to plants in the OL stage of licensing.

ENCLOSURE 2 i

U.S. NUCLEAR REGULATORY COMM;SSION Revision 1

" "~"" "

REGU LATORY G U DE OFFICE OF STANDARDS DEVELOPfWrX REGULATORY GUIDE 1.114 GUIDANCE ON DEING OPERATOR AT THE CONTROLS OF A NUCLEAR POWER PLANT A. INTRODUCTION and NRC regulations, (2) reviewing operating data, including data logging and review,in order to ensure Paragraph (k) of s50 54," Con iitions of Licenses,"

safe operation of the plant, and (3) being able to of 10 CFR Part 50, "I icensmg of Production and manually initiate engineered safet) f atures during Utihzation Facihties " requires that an operator or s arious transient and accident conditions.

senior operatar licensed pursuant to 10 UR Part 55, "Operaters' l_icenses," be present at the controls at in order for the operator at the controls of a all times during the operation of a facility.' General nuclear pow er plant to be able to carry out these and Design Cnterion 19c" Control Room," of Appendix other responsibilities in a timely fashion, he must gise A. " General Design Criteria for Nuc car Power his attention to the condition of the plant at all times.

plants," to 10 CFR Part 50 requires, in part that a lie must be alert in order to ensure that the plant is contrcl room be prosided from which actions can be operating safely and must be capable of taking action taken to eperate the nuclear power unit safely under to present any piogress toward condition that normal cenditions and to maintain the nuclear power might be unsafe. This is facilita' a control room plant in a safe condition under accident conditions.

design and layout in w hich all c,

>, instrumenta-As defined m 10 CFR ::50 Nt), the term " controls."

tion display s, and alarms required for the safe opers-w hen used with respect to nuclear reactors. means ap-tion. shutdow n, and coolJow n of the unit are readily parotus and mechanisms, the manipulation of which available to the operator in the control room.

di ectly affens the reactnit3 or pcwer level of the C. REGULATORY POSITION reactor T hn guide describes a method acceptable to the NRC staff for complying with the Commission's

1. The operator a't the controls of a nuclear povar m t.lations that require an operator to be present at plant should base an unobstructed view of and access d: contro!s of a nuclear power plant. The Advisor) to the operational control panels,' including in.

Committee on Reactor Safeguards has been con-strumentation displays and alarms, in order to be sulted concerning this guide and has concurred in the able to initiate prompt correctise action, when neces-regulatory position.

sary, on receipt of any indication (instrument move-mn r alarm) M a cha@ng conMom D. DISCUSSION

2. The operator at the controls should not no: mal-Operating enerience has shown that there is ly leave the area where continuous attention need for guidance with regard to acceptable methods (including visual surveillance of safety related annun-of complying with the Commission s requirement for ciators and instrumentation) can be given to reactor the presence of an operator at the cor. trois of a operating conditions and where he has access to the facility. The operator at the controls of a nuclear reactor controls. For example, the operator should power pLnt has.cany responsibihties, which include not routinely enter areas behind control panels where but are r;ot hmited to (!) adhering to the plant s technical specificatians, ph.in operating procedures, operanos control panels are contro; ranels that enable the operator at the controls to perforrn required manual safety fur..-

• line ind.:a:es substartne charge ' rom preuous issue.

nons and eqmpment surseillance and to rnonitor plant condi-Current 'L,ded Techn. cal Specificanons requre a laensed tions under norrnal and accident cond uens Operanonal control coerater i s ne present in the control room at all umes w hi e fuel panels include instrurnentanen for the reactor, reactor coolant r m the w

sptern. cea'rnreent and saf etpre!aud pre;en spterm USNRC REGULATORY GUIDES Comments eno,.o te seai io re sec ei. e u we comm.ss.or u s N.,cies,

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p; ant performance cannot be monitored. The sure that proper "li:' occurs, ad.inis:rative eperator at the contruts should not under any cir-procedures should b wri: ten to descr oe whn is re-cumstances leave the sunei.'ance area defined by quired. The adminis:ratise procedure should ' clude, regulatory position 3 for any nonemergency reason as a minimum, a der nition of proper relief (e g, w hat (e g.. to confer with others or for personal reasons) in fo rm ation is required to be passed cn and n ahout ahtaining a qualified relief operator at the acknowledged between the two opera;cro.

eentrols. In the esent of an emergency affecting the sarco of operations, the operator at the controls may

5. A single operator shou'd not c.ssu.e the momentarily be absent from the defined surseillance operator at-the-con:rols responsibility for ao or area in order to seriiy the receipt of an annunciator more nucleat power urits at the same time.

alarm or initiate correctise action, provided he re-mains within the confines of the control room.

D, IMPLEMENT ATION The purpose of this section is to pruvide ir. forma-

3. Administrative procedures should be es-tion to license appli: ants and 1::ensees regard.ng the tablished to define and outline (preferably with NRC staffs plans for using th.s regulatory pide.

sketches) specific ar"s withia the contro! room where the crerator at the controls should remain.

Tiiis guide reflects current 3RC staff practice.

The procedures should define the surveillance area Therefore, except in those case, in which the appli-and the areas that may be entered,in the esent of an ear t or heensee preposes an acceptable alternative cmergency affecting the safety of operations, by the method for complying with specified portions of the operator at the controls to s erify receipt of an annun-Ccmmission's regulations, the method de:cribed eiator alarm or initiate corrective action, herein is being and will continue to be used in the es aluation of submittals for operating licente er con-

4. Prior to assuming responsibility for being struction permit applications and the rerformance of operator at the controls, the relief operator should be licensees until this guide is re,ised as a result of sug-nroperly bnefed on the plant status. In order to en-gestions from the public or additional staff review.

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