ML19241B090
| ML19241B090 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/11/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Counsil W NORTHEAST NUCLEAR ENERGY CO. |
| References | |
| TASK-02-01.C, TASK-02-03.B, TASK-02-03.C, TASK-03-03.C, TASK-03-04.A, TASK-03-04.B, TASK-03-09, TASK-03-11, TASK-03-12, TASK-05-04, TASK-05-06, TASK-05-11.B, TASK-05-12.A, TASK-06-04, TASK-06-08, TASK-07-03, TASK-07-05, TASK-08-02, TASK-09-06, TASK-13-01, TASK-RR NUDOCS 7907110673 | |
| Download: ML19241B090 (7) | |
Text
A x 5/(f
+
0 UNITED STATES E D') eq (',,g NUCLE AR REGULATORY COMMISSION E
W ASHINGTON, D. C. 20555
%.dA,/. /
o,,
p June 11,1979 4
Docket No. 50-245 r
Mr. W. G. Counsil, Vice President Nuclear Engineering and Operations Northeast Nuclear Energy Cor:pany i
P. O. Box 270 i
Hartford, Connecticut 06101 l
Dear Mr. Counsil:
RE:
IMPLEMENTATION OF CATEGORY 2 AND 3 REGULATORY GdIDES IN THE SYSTEMATIC EVALUATION PROGRAM - MILLSTONE NUCLEAR POWER STATION UNIT NO. 1 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 censideration of the need for backfitting appears to be required for certain ideni.ified items of the regulatory position - these individual issues are i
[
such that existing plants need te be evaluated to j
determine their status with rejard to these safety
}
issues to detertaine the need ror 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 bo considered is also shown.
A copy of one Lategory 3 position, Regulatory Guide 1.114, Revision 1, " Guidance on Being Operator at the Controls of a Nuclear Power Fiant", is provided in.
To complete our evaluation of this spr.ific guide you are requested to provide c ommitment to meet the recommendations of the guide.
r, 4 q 7007110673
4 2-June 11,1979 fir. W. G. Counsil Please contact the assigned Project Manager for your facility if you have any question. or comments about these matters.
c Sincerely, O
s
/J6 /1 Dennis L. Zieman* Chief Operating Peactors Branch #2 Division of Operrting Reactors
Enclosures:
1.
List of Category 2 and 3 Positions 2.
Regulatory Guide 1.114 cc w/ enclosures:
See next page t
~ A T
~f*,
)
i
Mr. W. G. Counsil June 11, 1979 i
I cc w/ enclosures:
William H. Cuddy, Esquire Day, Berry & Howard Counselors at Law One Constitution Plaza Hartford, Connecticut 06103 Anthony Z. Roisman Natural Resources Defense Council 917 15th Street, N. W.
Washington, D. C.
20005 Northeast Nuclear Energy Company ATTN:
Superintendent Millstone Plant P. O. Box 1C8 Waterford, Connecticut 06385 i
Mr. James R. Himmelwright Northeast Utilities Service Company P. O. Box 270 Hartford, Connecticut 06101 I
Nuclear Regulatory Commission, Region I Of fice of Inspection and Enforcement I
ATTN:
John T. Shedlosky 631 Park Avenue King of Prussia, Pennsylvania 19406 Waterford Public Library Rope Ferry Road, Route 156 Waterford, Connecticut 06385 K M C, Inc.
ATTN:
Richard E. Schaffstall 1747 Pennsylvania Avenue, N. W.
i Suite 1050 Washington, D. C.
20006
_7 s
e e
4 ENCLOSURE 1 CATEGORY 2 AND 3 MATTERS TO BE ADDRESSED IN THE SEP I
1 CATEGORY 2 MATTER _S Document Number Revision
._Date Title Tooic i
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 ray, but need not, i
be considered.
i RG 1.59 2
8/77 Design Easis Floods for Nuclear II-3.B Power Plants i
RG 1.oJ 2
7/78 Electric Penetration Assemblies in III-12 Containment Structures for Light Water Cooled Nuclear Power Plants Evaluation of Ex9 osions' Postulated II-1.C 1
RG 1.91 1
2/7F to Occur on Transportation Routes Near Nuclear Power Plant Sites RG 1.102 1
9/76 Flood Protection for Nuclear Power II-3.B l
Plants RG 1.108 1
8/77 Periedic Testing of Diesel VIII-2 1
Generator Units used as Onsite Electric Power Systems at Huclear Power Plants RG 1.115 1
7/77 Prctection Ageinst Low-Trajectory III-4.3 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 Combination: for Class 1 III-ll Linear Type. Component Scopor s RG 1.133 0
7/77 Design Limits tnd Leading Co-tir.ations III-9 for Class 1 Plate-and Snell-Type III-11 Component Supports (Continued) g' 1
CATEGORY 2 MATTERS (COh'T ' D )
Continued Docurent Murrber Revision Date Title Tooic RG 1.137 0
1/78 Fuel Oil Syster for Standby VIII-2 Diesel Generators (Paragraph C.2)
BTP ASS Guidelines for Fire Protection for IX-6 9.5-1 1
Nuclear Power Plants (See licplementation Section. Section 0) 5TP HTES 5-7 4/77 Naterial Selection and Processing V-4 Guidelines for BWR Coolant Pressure Boundary Piping RG 1.141 0
4/78 Containment Isolation Provisions VI-4 for Fluid Systems G
. CATEGORY 3 MAT!TRS Document 3ymber Revision Date Title Topic RG 1.99 1
4/77 Effects of Resideal Elements on V-6 Predicted Radiation Damage to Reactor Yessel Materials (Paragraphs C.l 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 CRS #2 Controls of a Nuclear Power Plant RG 1.121 0
8/76 Bases for Plugging Degraded ?WR V-8 Steam Generator Tubes RG 1.127 1
3/78 Inspection of Water-Control Structures III-3.C Associated with Nuclear Power Plants R5B 5-1 1
1/78 B' ranch Technical Position: Design Require VII-3 rents of the Residual Best Removal System Y-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 (Paragraph C.3 - with additional eu' dance on paragraph C.3.d to be provided later)
RG 1.56 1
7/78 Maintenance of Water Puri_ty in V-12. A Boiling Vater Reactors 0
- l MATTERS THAT ARE NOT TO BE ADDRESSED 1.
Regulatory Guide 1.10S " 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, 00R 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 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 DOR /EEB on a generic basis.
Since ALARA issues were not incli ed in the f
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-Ccoled Nuclear Power Plants" -- This matter was determined, by Regulatory Requirements Review Committee, to be applicable to plants in the OL stage o' licensing.
g I
ENCLOSURE 2 U.S. NUCLEAR REGULATORY COMMISSION Revision 1 l
November 1976 t
REGUL ATORY GD DE OFFICE OF STANDARDS DEVELOPMENT 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 teview, in order to ensure Paragraph (k) of s50.54,"Condinons of Licenses."
safe operation of the plant. and (3) being able to of 10 CFR Part 50, " Licensing of Production and manualb initUte engineered safets features during Utilication Facihtie;,' requires that an operator or sarious tranut and accident con tions.
senior operator licensed pursuant to 10 CFR Part 55,
" Operators' Licenses," be present at the controls at in order for the operator at tlw controls of a al! times during the operation of a fa nity ' General nuclear power plant to be able to carry out these and Design Criterion 19 " Control Room," of Appendis other responsibilities in a timely fashion., he must give A, " General Design Criteria for Nuclear Pou r his attention to the condition of the plant at all times.
Plants," to 10 CFR Part 50 requires, in part, that a He must be alert in order to ensure that the plant is control room be prosided from which actions can be operating safely and must be capab e of takir:g action taken to operate the nuclear power unit safely under to present any progress toward < condinon that normal conditions and to maintain the nuclear power might be unsafe. This is fac;litated by control room plant in a safe condition under accident conditions.
design and layout in wnich all controls,instrumenta-As ufined in 10 CR 4502t), the term " controls.'
tion display s, and alarms recuired for the cafe opera-w hen used with respect to nuclear reactors, means ap-tion, shutdow n, and cooldow n of the unit are readily paratus and mechanisms, the manipulation of which available to the operator in the control room.
directly affects the reactisity or power lesel of the C. REGULATORY POSITION reactor. l his guide descobes 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 recuire an operator to be present at plant should hue an unobscucted siew of and access the con'
's of a nuclear puer plant. The Adsisor}
to the operational contro panels,; Meluding 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 corrective action, when neces-regulator, position.
sary, on receipt of any indication (instrument move-ment or alarm) of a changing condition.
B. DISCUSSION
- 2. The operator at the cortrols should not normal-Operanng experience has shown that there is a IV leave 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 w here he has access to the facihty. The operator at the controls of a nuclear reactor controls. For example, the operator should power plant has many respcnsibihties, which include not routinely enter areas behind control panels where but are not limited to (1) adhering to the plant s technical specifications, plant operating procedures Operatw/ contrgl panels are ontrol panels that enable the s
operator it the controh to perfor n required manual safety fune.
- Line ind ;ates suestantne chage from preuous issue-tions and equ.pment surveillan:c and to rnonitor plant condi-Currem vandard leenracal Specifications require a licersed tions under normal and accident andmons. Operatioralcontrol he prnent in tF.e cortrol room at aH tirres w bde fuel panek ;M_de instrumentation f ir the reactor. reactor ceo! ant enramr : 3 9 stem, s vtanment and safer.-related proce u stem a m the w USNRC REGULATORY G8)lDES commems s oso be wat to me secwen ci me co-u.oa u s weien,
.i c, & m.n e wnm e oc m Atewn Docmag ou Re g io% og en e,e,u.e s t a o e s c a-o sa a -n e...a.m e io t a e o.e -
a RC esatt o' imo'ecaerne g m oecio.c pa-s c' ic e cae m a s s ec ee+ a me io the v
Comm ss oa a *e Jetes t o oeee ste tocances o.s e, tae st.i".a e.a o g
,,,,,,,,,,,,,,,,,,,,3,,,,,,_
,,,,,,u,?,,,
... g n o e : 4. :. p ec o+ e m s or po st w i e r e s a c c.* a a's o t o o.s v.1 e g.co s a c e i o a r c h coata R e g w a'ow G. d es e e " i euts-utes f or re gs st+es sad cc mpaeme y
g,,g,,
,,s 6 s aoun
.+%
- e m.s no' e se s ve Seasomsoo-o d Hereat f rom those set own va y ag, yg,g
,p, y.,,,
,g tho g ndes. m e o er-c e:s t e.f, e s c ri ce o t es.s 80' tae f a d a g s te ov.sa e i
),, p, y,,.
,,gg,,
g y
,.g the isswance os c c me assas e of a pew i n ireese b e iae comm.ss oa g
go,.,,,,,,,,
,,,g,,,,g g
,,,.q,,,,,
sMe**'***aa*ea' P'ois coc a ic eae's ee.sec*ss'.ea w w eaes co - eatseaeingee
.,.m
.-o.o.e e, a m 6' e ' t " e s andg w e e-e e ses seat.o
.e te a r c o v m oa e's c c+
me, e oas sa eer.
,as..
e ao. e a s e..., t e i y a e. n.e,.n o e.,
c op.e oi at.s*,sg-oesme e,et
, e s e,..v ien er.<est.ac.c ooa g t he eo s < ce sou s'.
.e : 2+~
e..; t.om e r e ;.
a.. o ;. n n.
. e.t e, s.o s s se s.,eo is ia e U s es we, c3. ; a m-n,ss n e, esma gion DC 2%% As sem n e D e et - i O': c e of sier e e s Lt.em ame '
re e.-
plant performance cannot be monitored. The sure that proper relief occurs, administrative operator at the controls should not under any cir-procedures should be written to describe what is re-cumstances leave the surseillance area defined by quired. The administrative procedure should include, regulatory position 3 fer any nonemergency reason as a minimum, a definition of proper relief (e.g., what (e g., to confer with others or for personal reasons) information is required to be passed on and without obtaining a qualified relief operator at the acknowledged between the two operators).
controls. In the event of an emergency affecting the safety of operations, the operator at the controls may
- 5. A single cperator should not
. ssume the momentarily be absent from the defined surveillance operator-at the-controls responsibility for two or area in order to serify s ue receipt of an annunciator more nuclear power units at the same time.
alarm or initiate corrective action, provided he re-mains within the confines of the control room.
D. IMPLEMENTATION The purpose cf this sec: ion is to provide informa-
- 3. Administrative procedures should be es-tion to license applicants and licensees regarding the tablished to define and outline (preferably with NRC staff's plans for using this regulatory guide.
sketchesi specific areas within the control room where the operator at the controls should remain.
This guide reGens current NRC staff practice.
The procedures should define the surveillance area Therefore, except in those cases in which the appli-and the areas that may be entered,in the event of an cant or licensee proposes an acceptable alternative emergency affecting the safety of operations, by the method for complying vith specified portions of the crerator at the controls to serify receipt of an annun-Commission's regulations, the method described ciator alarm or initiate corrective action.
herein is being and will continue to be us:d in :he es aluation of submittals for operating license or con-
- 4. Prior to assuming responsibility for being struction permit applications and the performance of operator at the contro!s, the relief operator should be licensees until this guide is revised as a result of sug-properi: briefed on the plant status. In order to en-gestions from the pubiic or additional staff review.
F l
41 Lp u J
oE is 15
- 85 hs I!
m%
58' 3
0 5
i 5
2$ r3
., 8 % I3
- 2j 63 350 mn 5Ei
20 0; q
l l.1,4-2