ML20111C461

Forwards Addl Info on 19 Specific Agenda Items Re Detailed Control Room Design Review,Per SER Outstanding Issue 19 & NUREG-0737 Item I.D.1.Sample of How Need Characteristics of Instruments & Controls Determined Encl

ML20111C461
Person / Time
Site:	Seabrook
Issue date:	01/07/1985
From:	Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	Knighton G Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, TASK-1.D.1, TASK-TM SBN-748, NUDOCS 8501090298
Download: ML20111C461 (34)

Text

'

SEABROOK STATION e) (7

_. j Engineering Office b

rubec seMce of New Hampdte January 7, 1985 Now Hampshire Yankee Divleien SBN -748 T.F. B7.1.2 United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention:

Mr. George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing

References:

(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) USNRC Letter, dated December 6, 1984, " Summary of Meeting Between PSNH and the NRC Held on October 12, 1984, in Bethesda, Maryland", by V. Nerces (c) PSNH Letter, SBN-701, dated July 30,1934, " Response to DCRDR In-Progress Audit; SER Outstanding Issue No. 19; NUREG-073 7 Item I.D.1",

J. DeVincentis to G. W. Knighton

Subject:

Detailed Control Room Design Review; SER Outstanding Issue No. 19; NUREG-0737 Item I.D.1

Dear Sir:

On October 12, 1984, our representatives met with the Seabrook Licensing Project Manager and Human Factors Engineering Branch reviewer regarding cur Detailed Control Room Design Review (DCRDR). At this meeting, we committed to provide additional information on nineteen specific agenda items. This additional information for each of the nineteen items is attached to this letter ( Attachment A).

In Reference (b) you indicated the following:

'The meeting primarily focused on the applicant's incompleteness of their submitted task analysis and what the applicant has to accomplish in order to complete it.

In particular, it was noted that for each instrument and control used to implement the emergency operating procedures, there should be an auditable record of how the "need" characteristics of the instruments and controls were determined. These "need" characteristics should be derived from the information and control needs identified in the background documentation of Revision 1 of the ERG or from plant specific information.'

B501090298 850107 PDR ADOCK 05000443 E

PDR 90 1

1 P.O. Box 300 Seabrook, NH 03874. Telephone (603) 474-9521 i

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. 4-United' States Nuclear Regulatory Cosmission

Attention:

Mr. George W. Knighton Page 2 Att'achment-B to this letter provides a sample of how the need

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characteristics of the instruments and controls were determined.. This documentation'will'he available for your inspection for each of our Emergency Operating Procedures. The sample swas performed on Emergency Operating.

Procedure E-O (Reactor Trip or Safety Injection). Please note.that the sample task analysis is not complete, it has been included to delineate our task analysis methodology and format.only.

In light of the substantial information and numerous commitments ve.have tendered during your comprehensive review of. this Safety Evaluation Report Outstanding Issue, we would expect the.next Safety Evaluation Report Supplement to ' address DCRDR and to remove it from the list of. Outstanding.

' Issues.

t Very truly yours, John DeVincentis, Director Engineering and Licensing cc: Atomic' Safety and Licensing-Board Service List Attachments i

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i William S. Jordan, III Dians Curran Harmon, Weiss & Jordan Brentwood Board of Selectmen 20001 S Street N.W.

RED Dalton Road

~ Suite 430 Brentwood, New Hampshire 03833 Washington, D.C.

20009 Robcrt G. Perlis 1

Office of the Executive Legal Director Edward F. Meany U.S. Nuclear Regulatory Commission Designated Representative of Washington, DC 20555 the Town of Rye 155 Washington Road Robert A. Backus Esquire Rye, NH 03870 116 Lowell Street P.O. Box 516 Calvin A. Canney Mancehster, NH 03105 City Manager City Hall Philip Ahrens, Esquire 126 Daniel Street Assistant Attorney General Portsmouth, NH 03801 Department of the Attorney General Augusta ME 04333 Dana Bisbee, Esquire Assistant Atterney General Mr. John B. Tanzer Office of the Attorney General Designated Representative of 208 State House Annex the Town of Hampton Concord, NH 03301 5 Morningside Drive Hampton, NH 03842 Anne Verge, Chairperson Board of Selectmen Roberta C. Pevear Town Hall Designated Representative of South Hampton, NH 03642 the Town of Hampton Falls Drinkwater Road Patrick J. McKeon Hampton Falls, NH 03844 Selectmen's Office 10 Cer. tral Road Mrs. Sandra Gavutis Rye, NH 03670 Designated Representative of the Town of Kensington Carole F. Kagan, Esq.

RFD 1 Atomic Safety and Licensing Board Panel East Kingston, NH 03827 U.S. Nuclear Regulatory Commission Jo Ann Shotwell, Esquire Assistant Attorney General Mr. Angie Machiros Environmental Protection Bureau Chairman of the Board of Selectmen-Department of the Attorney General Town of Newbury One Ashburton Place, 19th Floor Newbury, MA 01950 Boston, MA 02108 Town Manager's Office Senator Gordon J. Humphrey Town Hall - Friend Street U.S. Senate Amesbury, Ma.

01913 Washington, DC 20510 (Attn: Tom Burack)

Senator Gordon J. Humphrey 1 Pillsbury Street Diana P. Randall Concord, NH 03301 70 Collins Street (Attn: Herb Boynton)

SEabrook, NH 03874 Richard E. Sullivan, Mayor Donald E. Chick City Hall Town Manager Newburyport, MA 01950 Town of'Exeter 10 Front Street Exeter, NH 03833

~ ~ ~

I Page 1 of 3

ATTACHMENT A of SBN-748

1. -

The NRC felt'that we had still not satisfied the requirements for the determination.of necessary characteristics for instruments and controls associated-with. procedure tasks. We agreed to do further work in this area.

-As indicate'd in the cover letter, Attachment B contains a sample of what we will do. regarding Instrument and Control (I&C) needs and requirements.

Attachment B contains a sample of what will be done for all Emergency Procedures and.the format and method that will be used. Due toLtime 9-constraints and Human Factors Consultant availability, the sample is not I"

~

completely developed. It should be treated as a draf t document except i

for the format and method used.

!2.[ NRC disagrees with our decision to complete the review of auditory

5 H signals and HVAC after commercial operation. They want it-complete prior to reaching 5% power.

q.

x This is the result of a misunderstanding between ourselves and the NRC.

We have done a great deal of work in the auditory signal area with respect-to alarms in the control room. HEDs have been developed and submitted:to NRC for review. A preliminary HVAC evaluation for the area will.be completed-prior to startup, and HEDs will be developed if necessary.

[

It;is our-intention to complete the final. evaluation of the auditory area

~

when the plant is fully operational, with a normal level of sound

available; and that.the HVAC will be fully reviewed after a yearly cooling and heating. cycle has been experienced, again with the plant -

operational. Much of the review work has been done or will be done before plant operation, but the final evaluation cannot be completed ;

-until after plant operation.'

-3.

.From. Appendix, Part C, Item 3.4 of Reference (c)

A first out priority has been~ developed for Safety Injection actuation.

_ ' The three conditions which initiate SI are now on separate lights,;and first out' indication is provided.

4. - : From Appendix, Part C, Item 5.24 of Reference (c)

The priority on the ' review 'of RCP aimmeter range will be changed to 3C.

l5.

From Appendix, Part D,. Item 5.63 of Reference (c).

The s' team generator water, level recorders on Panel FF are multispeed recorders.

6.

zFrom' Appendix,.Part D,-Item'8.48 of Reference.(c)

Drawing 9763-F-510115 and two. photos have been submitted to the Htman Factors Branch'to further describe the problem and our resolution.

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Page 2 of 3

.w ATTACHMENT A of SBN-748 i

' 7. -

From Appendix, Part D, Item 9.8 of Reference (c)

'A marked-up Drawing 9763-F-510104, two photos, and an overlay have been submitted to the. Human Factors Branch to further describe the resolution of the problem.

8.:

-From-List of New HEDs, Item 0;17 of Reference (c)

~ All problem labels and/or procedures for Remote Safe Shutdown will be corrected.

1 9.-

From List of New HEDs, Item 0.19 of Reference (c)-

The pressurizer pressure indicator will be reviewed to assure the necessary range and accuracy to allow the operator to monitor pressure during the cooldown.

~

' The'following items are incomplete. Review or submittal will be completed as

. indicated in each item..

10.'

From' Appendix, Part C, Item 3.3 of Reference (c)

The Radiation Monitoring System will be reviewed, and resolution of our HEDs submitted to the NRC at least 120 days PTLF. ' Priority 2A.

11. : From Appendix, Part C, Item 4.8 of Ref erence (c)

The MSIV panel'will be reviewed and resolution of any HEDs submitted to the NRC at least 120 days PTLF.'. Priority ' 2 C.

12.. From Appendix, Part C, Item 5.29 of Reference'(c)

' The NRC disagrees with.the use of a hard copy of the status light :

-- matrix. This item will be,further reviewed by our. Review Team.

Resolution of the issue will be submitted to the NRC at least 120 days PTLF.

13.

From' Appendix, Part C, Item 6.50 of Reference (c)

The color study remains to.be completed.

It will.be submitted to the NRC at:least 120 days.PTLF.

314.. From Appendix, Part C, Item 8.24 of Reference _(c).

The fire panel remains to be-reviewed. The results of the review will.be-

. submitted to the NRC at least.120 days PILF.

.15..JFrom Appendix,.Part D, Item 9.7 of Reference (c)-

(The: Licensee. Response regarding the Steam. Dump meter on Panel FF-1 was unclear to-the NRC.-'It will be clarified and resubmitted for review at least 120 days FILF..

Ll6. From List of New HEDs, Items L1, 2, N2, 4 of Reference (c)

" The -NRC has : taken the position that all Annunciator HEDs must-be fixed before startup. -We are presently evaluating this issue.. The results of ithe evaluation will-be submitted at least 120 days PILF.

Page 3 of 3 e

ATTACHMENT A of SBN-748

17. ' From List. of New HEDs, Item 0.3 of' Reference (c)

A moveable bench for the atmospheric dump controllers was proposed. The p.

NRC position is that-a moveable bench is unacceptable. We are reviewing this. item and will submit our resolutica at least 120 days PTLF.

18.

From-List of New HEDs, Item P.1 of Reference (c)

A description of the method for ensuring that procedural documents are returned to the rack-in proper order will be submitted at least 120 days PTLF.

19.

From List of New HEDs, Item Q.2 of Reference (c)

The schedule for the addition of hierarchial labeling is under review..

It will be submitted at least 120 days PTLF.

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CSS Peep A. UntMigo Posittee tedicattee of Standard 1 Dpe D ourip toestag tangen 0 95 Aaps CSS fil. OPEN fly posities todteatles Staedard 5 2

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CCF flew tadteater.

SET flew indleater Analog indlaster Type 9 CMt3 FOR FLOW TMR00CM Ranges 0 1000 Spa CAT 2 t!T P4TM b.

RCS pressere = LESS TMAN RCS pressere tedteatten Amate$ tedicaties TFra C 1640 FStG Range 0 2500 PS14 CAT 1 Tatee to be read 1640 e

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$1 pep flow tedicatets.

$1 flow indleatete 4ee Amates Ledteatete Type 9 CNEOL FOR FLOW per peamp Raege 0 000 gpo CAT 1 TRA!9 A TRAIM S d.

RCS presente. LESS TMAS RCS pressere tedicattee Amateg ledttattee Type C 260 PS!4 Ranges 0 700 PStG CAT 1 Tatue to be reads 260 PStG e.

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CHEOL FOR FLOW pet pey Ranges 1 5000 spe CAT 2 TRA11 A TRA11 S 16 Tettfy tFW Flew. CRtAttR IW flew teditattee foi Amateg ledteattee Type 0 l

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Ranges 9 191 spo CAT 1 T. tee t. se reae. 41a FtoW TO AT stiST TWO Sc.

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Standate 1 Tf te 9 CAT 2 FT.42248, FLOW C04 TROL 091 i stee C

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Mammally start peeps and yesitive tedieettee of Standard 1 g

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peps reestag and v17 tantes 9 63 4eps posttles.

Standarfs 1 4 5 Maneatly start peeps. E positive todteattee of Standard L g

proper flee ese 'H)T be partpe reenteg and vle Ranges 4 399 spe estantlebed T4J go to f4 peettles.

Standards 3 & S 4.1. At3901SL To LOSS OF SECONDART MEAT S11K, STEP 1 Massally allge vetwee se Settches and ledteatles Standarde 3 & S g

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III* O TP valves to a SG era valve peettlee Standard $

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$4 pressere tedteattee testes tedicattee If*g taeges 0 1320 9514 I*

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PROCEDURE Euts eIt ACTION /ttPECTED RESPOM18

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ADfttLSt CO*rr1 #1R.94L Court 1 throttle valve WARtnW RAMFA W art 0W R A*18 Contateneet pressere Analog ledteettee g

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TMAS St Talse to be read 4.3 PS14 17 eee Seltshes & tedieettee Staedard S g

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Settsk for etese deep Setten postatoes

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ACT16N/ttPECTED RESPOMSt 53 DistG1 14C JTEF TASK /SU9 TASK

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PORTe. CLOSED Tle peettles ledteatten Standard 5 Type C CAT 1 LTOP SETP01NT CURVE FlcURE t.0 1 o

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Wereat PRER spray valves.

Vle peettles todteattee Standard 5 Type O CLOStB CAT 3 NOTE Seat lejeettee flew sheeld bi test teleettee flew ese Amates todteattees Type D estataleed to all RCFa.

per pmp Ranges 0 20 spe CAT 3 21 Check If RCPe Sheeld Se stoppeds a.

fitab Weed ECCS pumps. AT Posttive todtaattee of Standard 1 Type O LEAST ONE LOWMt w pumpo reentes Ranges 0 95 Amps C47 3 Range 0 73 Ampo CCP 0R.

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RCS subseetteg. Ltst RCS subesettag ledtes.

Amates teditattee type &

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Step all RCPe Peettive tedleettee of Standard 1 & 2 Type D punpa set tweetes Cat 1 ft Check If SG Pressere Senadar1 to totaats 4.

Check presseres le ett 80 pressere tedlastlee Analog todteattee Type 0 e

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Telee to be read 334$

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T4t4 eeee Tey eleoe ate blee It bleek RCS temp (VR)

Aeoles testatten Type C volve see 407 he eTesed, toege 0 700'r CAT 1 Tutt go teTl, LOSS OF IIAITfIt 04 SRC0404tf C00LA41.Settches and ladleottee Standard 3 & 5 Type C S tep 1.

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IP Pett pressere less thee Pressertser pressere heeleg todisettee Type C TTse pets, m aeseellr todtsettee tease 0.lson ella car i eleoe valves. IP volves Telee to read 3260 een wyf be sleeU, Turg stes PS14 ACP( W eepplytog fe M estof volve(s).

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Radiattee todteattee Analog ledteatten Type A WORMAL OW EACM List for sesh este stesellee taeges later CAT &

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Step 1 27 lettlete Meeltestes of Set CttttCAL SAFtTT Cattleel Safety remettes MwCitou ATTACMgegt Statee Trees "A".

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