ML19224D375

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

ML19224D375
Person / Time
Site:	Yankee Rowe
Issue date:	06/11/1979
From:	Ziemann D Office of Nuclear Reactor Regulation
To:	Groce R YANKEE ATOMIC ELECTRIC CO.
References
TASK-***, TASK-RR NUDOCS 7907110661
Download: ML19224D375 (7)

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June 11,1979 Docket No. EU-29 Mr. Robert H. Groce Licensing Engineer Yankee Atomic Electric Company 20 Turnpi', Road Westboro, riassachusetts 01581

Dear Mr. Groce:

RE:

IMPLEMENTATION OF CATEGORY 2 AND 3 REGULATORY GUIDES IN THE SYSTEMATIC EVALUATION PROGRAM - YANKEE R0WE ATOMIC POWER STATION In the Systematic Evaluation Program for your facility we plan to address Regulatory Guides and other staff positiens that have been classified as Category 2 or 3 for implementation by our Regulatory Reauirements Review Committee.

Category 2 and Category 3 are defined as follows:

r jery 2:

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

Category 3:

Clearly backfit.

Existing plants should be evaluated to determihe whetner 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 c.urrently plcn 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 Nuclear Power Plant", is provided in Encl osure 2.

To complete our evaluaticn of this specific guice you are requested to provide a commitment to meet thc recorsaendations of the guide.

7007110 g3(15 33 6

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

Sincerely, MY WM DennisL.Ziemann,fhief Operating ReactorYBranch #2 Division of Operating Reactors

Enclosures:

1.

List of Category 2 and 3 Positions 2.

Regulatory Guide 1.114 i

cc w/ enclosures:

See next page

}

i 315 337

Mr. Robert H. G*oce June 11, 1979 cc w/ enclosures:

Mr. Lawrence E. Minnick, President Yankee Atomic Electric Company 20 Turnpike Road Westboro, Massachusetts 01581 Greenfield Community Collega 1 College Drive Greenfieid, Massachusetts 01301 K M C, Inc.

ATTN:

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

Suite 1050 Washington, D. C.

20006 315 338

ENCLOSURE 1 CATEGORY 2 AND 3 MATTERS TO BE ADDRESSED IN THE SEP CATEGORY 2 M)*TERS Document Nuncer Revision Date Title Tooic 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 Ennineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Lnits of Light Water Cooled Nuclear Fower Plants (Revision 2 has been putlished but the changes frce Revision.1 to Revision 2 may, but need not, be considered.

RG 1.59 2

8/77 Design Basis Floods for Nuclear II-3.B Power Plants RG 1.63 2

7/78 Electric Penetration Assemblier. in III-12 Contain ent Structures for Light Water Cooled Nuclear Power Plants P.G 1.91 1

2/78 Evaluation of Explosions' Postulated II-1.C to Occur on Transportation Routes Near Nuclear Power Plant Sites RG 1.102 1

9/76 Flood Protection for Nuclear [ower II-3.B Plants RG 1.108 1

8/77 Periodic Testirrg of Diesel VIII-2 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 RG 1.117 1

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

1/78 Service Limits and Leading III-9 Comoination: for Class 1 III-ll Linear Type Compenent Support:

RG 1.130 0

7/77 Design Limits and Loading Cccainatiens III c for Class 1 Plate-and Snell-Type III-ll Cceponenc Supports (Contir.ed) 315 33?

CATEGORY 2 MATTERS (COh"r ' D )

Continued Document Number Revision Date Title Tooic RG 1.137 0

1/78 Fuel Oil Systees for Standby VIII-2 Diesel Generators (Paragraph C.2)

BT? ASB Guidelines for Fire Protection for IX-6 9.5-1 1

Nuclear Pruer Plants (See Icplemntation Section Section 0)

BTP MTEB 5-7 4/77 Material Selection and Processing V-4 Guidelinas for BWR Coolant Pressure Boundary Piping RG 1.141 0

4/78 Containment Isolation Provisions VI-4 for Fluid Systems 315 340

. CMTGORY 3 MA'rTERS Document Murt e r _ Revision Date Title Topic RG 1.99 1

4/77 Effects of Residual Eler.erits 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 #2 Controls of a Nuclear Power Plant RG 1.121 0

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

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

1/78 Branch Technical Position: Design Require VII-3 rents of the Residual Heat Removal Systu V-II.B R5B 5-2 0

3/78 Branch Technical Position: Reactor V-6 Coolant System Overpressurization Protection RG 1.97 1

8/77 Instrumentation for Light Water VII-5 Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident (ParagraphC.?-withadditional guidance on paragraph C.3.d to be providerd later)

RG 1.56 1

7/78 Maintenance of Water Purity in Y-12. A Boiling Water Reactors 315 3Al

-A-MATTERS THAT ARE NOT TO BE ADDRESSED 1.

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

However, D0R generic action on specific instrumentation such as LPRM drift 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 Relevant to Ensuring That Occupational Radiation Exposu-e at Nuclear Power Stations Will Be As Low As is Reasonably Achievable (Nuclear Power Reactors)" -

This matter is presentiy being proposed for resolution by DOR /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 Guide 1.68.2 " Initial Startup Test Program to Demonstrate Remote Shutdown Capability for Water-Cocled Nuclear Power Plants" -- This matter was determined, by Regulatory Requirements Review Committee, to be applicable to plants in the OL stage of licensing.

9 M

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Et! CLOSURE 2 U.S. NUCLEAR REGULATORY COMMISSION Revision 1

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REGUuTORY GUBDE OFFICE OF STANDARDS DEVELOPMENT REGULATORY GUIDE 1114 GUIDANCE ON BEING OPERATOR AT THE CONTROLS OF A NUCLEAR POWER PLANT A. INTRODUCTION and NRC regulations; (2) reewing operating data, including data logging and review,in order tc :nsure Paragraph (k) of j50.54,"Conditionc of Licenses,"

safe operatian of

..e plant; and (3) being able to of 10 CFR Part 50, " Licensing of Pradt.ct:on ard manually initiate engineered safety features during Utilization Facilities," requires that an operator or various transient and accident conditions.

senior operator licensed pursuant to 10 CFR Part !5,

" Operators' t.icenses," be present at the controls at in order for the operator at the controls of a all times c'aring th operation of a facility.' Gen:ral nuclear power plant to be able to carry out these and Design U erion ", " Control Room " of Appendix other responsibilities in a timely fashion, he must give t

A.'

- *neral Design Criteria for Nuclear Power his attention to the condition of the plut at all times Piant- ' to 10 CFR Part 50 requires, in part, that a He must be aleit in order to ensure that the plant is cont ol room be provided from which zedc"< can be operating safely and must be capable of taking action taken to operate the nuclear power unit safelv under to present any progress toward a condition that normal conditions and to maintain the nuclear power might be unsafe. This is facilitated by control room plant in safe condition under accident conditions.

design and layout in which all controls,instrumenta-As defined in :0 CFR ;50.2(t). the term "controlsJ tion displays, and alarms required for the safe opera-a hen used with resrect to nuclear reactors, means ap-tion. shutdow n, and cooldown of the unit are readily paratus and mechanisms, the manipulation of which aviiable to the operator in the control room, directly affects thc reactisity or power lesel of the C. REGULATORY POSITION reactor This 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 power regulations that require an operator te be present at plant should base an unobstructed view of and access the contra!s of a nuclear power plant. The Advisory to the operational cootrol panels,' including in-Committee on Reactor Safeguaros has been con-strumentation displays and alarms, in order to be sulted concerning this guide and has concurred m the able te initiate prompt corrective action, when neces-

.cgulatory position.

.sary, on receipt of any indication (instrument move-

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• " "" E "E D. DISCUSSION

2. The operator at the controls should not normal-Operating experience has shown that there is ly eave the area where continuous attention need for guidance with regard to acceptable methods (including visual surseillance 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 controls of a operating conditions and where he has access to the facility. The operator at.he controls of a nuclear reactor controls. For example, the operator should powec plant has many responsibilities, which mclude not routinely enter areas behinu control panels where but are not limited to (1) adhering to the plant s technical specifications, plant operating procedures, c er.monai contrel p.,nek are control panels that enable the r

operator at the controk to perform required manual safet) func-Line indcates substa,tne char:ge from previous issue.

nons and equip., ent survedlance and to monitor plant condi.

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.t bndard Tec% cal Specificanorn regare a hcensed nons under normat and accdent carditions Operational cor,troi r,, he present in the control room at all times while fuel panch inide instrurrentanon for the reactor. reactor coolant o

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ystem cortamrnent. and safetprelated prmess estems

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USNRC RE GULATORY GUIDES c m - m,.s 1 d. s e a, i.,b e S.c.... v.. w. c.. m.u..a o s

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plant performance cannot be monitored. The sure that proper relief occurs, c f mini".rative operator at the controls should not under any cir-procedures should be written to des;r.se what is re-cumstance leave the surseillance area defined by quired. The administrative procedure saould include, regulato, position 3 for any nonemergency reason as a minimum, a definition ef proper re'ief(e g, w hat i

(e g to confer with others or for personal reasons) information is required to be passed en and without obtaining a qual d relief operator at the acknowledged between the,wo operators).

eentroh in the esent of an emergency affecting the safety ef operations, the operator at the controls may

5. A single operator snauld not assu.e the momentarily be absent from the defined surveillance operator-at-the-controls reronsibility for two or i

area in order to verify the receipt of an annunciator more nuclear power units the same time.

alarm er initiate corrective action, prov ded he re-mains adhin the confines of the control room.

D. IMPLEMENTATION The purpose of this section is to provide informa-

3. Administratis e procedures should be as-tion to license appbcants an ' licensees regard.ng the tablished to define and outline (preferably with NRC stats plans fer usir.c this regulatory guide.

sketches) specific areas within the control room where the operator at the controls should remain.

This guide reflects current NRC staff practice.

The pro:edures should define the surveillance area Therefore, except in those <2ses in v ' :ch the a pli-and the areas that may be entered,in the event of an cant or licensee preposes an acce; me alternative emergency affecting the safety of operations, by the method for complying with specified portions of the operaur at the controls to s erify receipt of an annun-Commissioni regulations, the method described ciator alarm or initiate corrective action.

herein is being and will continue to be used ir the evaluation of submittals for opt iting license er con-

4. Prior to assuming responsibility for being struction permit applications a.u the performance of operator at the controls, the relief operator should be licensees until this guide is revis d as a result of sug-properly briefed on the plant status. In order to en-gestions from the public or addnional staff resiew.

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