ML20247Q676

Intervenors Second Informational Suppl to Low Power Contentions Filed on 890721 & 0828.* Incorporates Encl Plant Startup Test Procedure 1-ST-22,Rev 2 Into Low Power Testing Contentions.W/Supporting Info & Certificate of Svc

ML20247Q676
Person / Time
Site:	Seabrook
Issue date:	09/22/1989
From:	Traficonte J MASSACHUSETTS, COMMONWEALTH OF, NEW ENGLAND COALITION ON NUCLEAR POLLUTION, SEACOAST ANTI-POLLUTION LEAGUE
To:	Atomic Safety and Licensing Board Panel
References
CON-#389-9212 OL, NUDOCS 8909290064
Download: ML20247Q676 (22)

Text

- _ _ _ - _ _ _ - _ _.

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DDMETED t." N C UNITED STATES OF AMERICA

. NUCLEAR REGULATORY COMMISSION P

89 SEP 25 P3 :53 ATOMIC SAFETY AND LICENSING BOARD Of f E,

L Before the Administrative Judges:

DOCmi ' r.

r s ;. g i. ' s "

i i;

Ivan W.

Smith, Chair. man Dr. Richard F.

Cole Kenneth A. McCollom

~)

In the' Matter of

)

Docket Nos. 50-443-OL

)

50-444-OL PUBLIC SERVICE COMPANY

)

(Off-Site EP)

OF NEW HAMPSHIRE,.EI AL.

)

)

(Seabrook Station, Units 1 and 2)

)

September 22, 1989

)

INTERVENERS' SECOND INFORMATIONAL SUPPLEMENT TO THEIR LOW-POWER CONTENTIONS FILED ON JULY 21 AND AUGl[SL28. 1989

(

The Massachusetts Attorney General

(" Mass AG"), tne Seacoast Anti-Pollutio9 League (~"SAPL") and the New England Coalition on Nuclear Pollution ("NECNP") (collectively, the I

" Interveners") submit the two attached documects as additional

-support for the low-power testing contentions filed to date.

Attached as Exhibit 1 is the Seabrook Station Startup Test Procedure 1-ST-22, Rev. 2 received by the Mass AG on September 22, 1989 from the NRC in response to a FOIA request.

The Interveners incorporate this document into their low-power

' testing contentions including $3.0 setting forth the

" Prerequisites", S4.0 identifying "Special Precautions" and j

$5.0 labelled " Initial Conditions."

8909290064 890922 PDR ADOCK 05000443 g

PDR

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f Attached as Exhibit 2'is.a September 15 letter to the Applicants'from Robert'Gallo, Chief of the Operations Branch of I-the Division of. Reactor Safety (" September letter").

(This letter is dated September 15, but was not postmarked until.

September 20 and was not received by the Mass.AG until Ir September 22, 1989.)

As the September letter indicates, the g

"NRC. Staff is no longer confident that the present level of-operator training and overall proficiency is adequate to

. support full-power licensing.

The September letter indicates:

1.

As a result of the enforcement meeting held on September 7, 1989 to discuss and review the June low-power testing events, the NRC has decided to conduct an " evaluation l

of operator proficiency";

2.

These further tests will he conducted during the week of December 11, 1989 and will involve all shift operating crews; L

3, These tests will not be limited to the use of the l

Emergency Operating Procedures ("EOPs") but will involve a demonstration of broad operational knowledge and proficiency in l

response to a series of NRC-developed scenarios.

i The Interveners incorporate this document into their July 21 and August 28, 1989 submittals.

It is now clear beyond peradventure that the NRC Staff has determined that the low-power testing events present an issue material to the issuance of a full-power license: yint, are the Applicants' operators adequately trained or otherwise able to safely operate the Seabrook reactor?

In order to determine whether it l I

a can make the-requisite finding in this. regard, the_NRC Staff

)

has decided to require further perf0rmance testing and evaluation.1#

Thus, certain representations made by Staff attorneys in the Staff's Response to the Interveners' July 21 and August 28 filings are'no longer (if they were ever) accurate.

In their l

' August 22, 1989 Response to Interveners' July 21 Motion at

~17-18, the Staff stated:

1 The Staff continues to believe, as supported by its inspection report findings, that personnel involved.in the operations of the facility are well' trained, dedicated, highly motivated,.and responsive to NRC concerns Based on the Staff's experience and knowledge of the Applicants' performance and considering all of the circumstances noted above, the mistakes made by management and operating personnel during the natural circulation startup test appear to be an isolated occurence.

- 1/

The Interveners hope the follcwing exchange during the September 6,- 1989 public meeting shaped the NRC's views in this regard:

MR. WEINBERG:

Let's just use an example.

Let's say that somebody were to flunk their junior year in high school, and they said I~ realized that I failed, would you therefore advance them on to further levels?

MR. MARTIN:

No, I would make them take the junior year again.

MR. WEINBERG:

And will this happen, will they have to go back to Point A before they can go to any kind of full-power licensing?

I MR. MARTIN:

We have to be satisfied that the corrective j

action is capable of preventing recurrence and then we have to verify that the licensee has successfully prevented any future event.

We are going to have to monitor their corrective action, that is fact.

' Transcript of September 6 Public Meeting at 100-101. 1

[

Similarly, in their September 14, 1989 Response to Interveners' August 28 filing at 11, the Staff asserted that the low-power testing events are not material to a licensing decision arguing:

[C]ontentions may not be based upon isolated incidents.

Obviously, the Staff has now determined that the June events are significant enough to require further inquiry into the Seabrook operators' proficiency in the form of further evaluation and testing before islinance el a full-ncLwig licenER.

COMMONWEALTH OF MASSACHUSETTS JAMES M.

SHANNON ATTORNEY GENERAL

/

/

1/$

[ '/C6 ~ D

/[ Chief,

~

ohn Traficonte Nuclear Safety Unit f, Department af the Attorney General

/ One Ashburton place Bo s ton, MA 02108-1698 (617) 727-2200 DATED:

September 22, 1989

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• ' Appendix 8 STPD Rev. 2

- Form 1 SEABROOK STATION Startup Test Procedure 1 -ST-22 Rev.

2

Title:

NATURAL CIRCULATION TEST Prepared by:

R. A. Gwinn Date:

J/SO/ff DETERMINATION OF 10CFR50.59 APPLICABILITY:

1.

Does this procedure or revision:

\\

a.

Make changes in the facility as described C Yes I X l No in the FSAR?

b.

Make changes in procedures as described R Yes l x l Wo in the FSAR?

c.

Involve tests or exterfments root described l

lYes N No in the FSAR?

d.

Involve changes to the existing Operating R Yes

[TlNo i

License or require additional license requirements?

2.

If any of the above questions are answered yes, s

a safety evaluation per NHY Procedure 11210 is required.

l l

de 3/#//JV Approval Recomended by:

Startup Manager

' D&te

~

Approved:

Md Ih '9 Statio n an r

Date s o < r_ u N 53 l

EXHIBIT 1

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1-ST-22 Rev. 2 Page 1 of 12 SEABROOK STATION STARTUP TEST PROCEDURE 1-ST-22 NATURAL CIRCULATION TEST Prepared by:

R. A. Gwinn SECTION TITLE PAGE 1.0 OBJECTIVE 2

. 2.0 REFER'INCES 2

3.0 PREREQUISITES 2

4.0 SPECIAL PRECAUTIONS 3

5.0 INITIAL CONDITIONS 4

6.0 TEST INSTRUCTIONS S

7.0 FINAL CONDITIONS 12 8.0 ACCEPTANCE CRITERIA 12 9.0 ATTACHMENTS 12

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_2 1-ST-22 Rev. 2 Page 2 of 12 1.0 OBJECTIVE l

This test will detennine several natural circulation characteristics and will demonstrate the ability to remove heat from the reactor coolant system using natural circulation. The characteristics to be determined include:

time necessary,to stabilize natural circulation; reactor coolant flow distribution; depressurization rate following loss of pressurizer heaters; depressurization rate using auxiliary spray; effect of charging flow and steam flow on subcooling margin; subcooling monitor performance.

2.0 REFERENCES

CURRENT NO.

TITLE REVISION REVISION 2.1 1-ST-1. Startuo Program Administration 2

2.2 Seabrook Station Technical Specifications Amend 1 Precautions, Limitations and Setpoints for 2.3 the Westinghouse NSSS 2

Seacrook Station FSAR, RAI Response 2.4 640.51-4t 56 2.5 ES-0.2. Natural Circulation Cooldown 6

2.6

!ASME Steam Tables 5th Ed.

SeaDrock Station FSAR, TaDie 14.2-5, "

2,.7 Item 22 Amend 61 i

2.8 Startuo Test Pregram_ Description i

2 INITIALS /0 ATE I

.3---

3.0 PRERE0VISITES

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3.1 The test director has reviewed the latest revisions of the applicable references to detennine if any system changes that have been made will affect the test performance.

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3.2 Personnel involved with the perfonnance of this procedure

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have been briefed on the procedure content and informed of their respective duties.

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3.3 The Temporary Modifications Log and Danger Tag Log have been reviewed to identify and correct any itens which may restrict the performance of the test.

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3.4 Instrument inputs to GETARS is arranged to include those identified by Attachment 9.4, as a minimum, and at a scan rate of less than or equal to 250 millisecond interval.

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3.5 The reactor coolant system flow measurement test, 1-ST-11, has been completed and the RCS flow instrumentation has been adjusted as required.

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Page 3 of 12 INITIALS /DATC 3.6 The following systems are available for use:

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3.6.1 Station Computer.

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3.6.2

• Service Air.

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3.6.3 Instrument Air.

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3.6.4 Circulatirig Water System.

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3.6.5 Main Condenser.

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3.6.6 Chemical and Volume Control System (including auxiliary spray).

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3.6.7 Steam Dump (including atmospheric relief valves).

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3.7 The station Operations Manager and Training Center Manager have been notified of the estimated start of the test, so thatasmanyOperationspersonnelaspossiblemayjwitness the test. (See Reference 2.4.)

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3.0 The Unit Shift Supervisor has been notified that the test is about to comence.

3,,,,3, g M i 4.0 SPECIAL PRECAUTIONS u,

3. it..s

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t.1 The requirements of Technical Specifications 3.4.1.1 or 3.10.4 and the associated surveillance requirements must be adhered to throughout the performance of this test.

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4.2 Do not exceed 5% thermal power at any time during this test.

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4.3 The normal AT and Tava indications will be unreliable during natural circulation conditions. The wide range hot and cold leg indications should be used to calculate these values.

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4.4. Cold leg temperature should be maintained at approximately the initial (pre-RCP trip) temperature.or greater than 550*F unless otherwise directed.

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4.5 All personnel participating in the test should be aware that the moderator temperature coefficient is itear zero and may change sign during the test. This is to reduce reactivity feedback effects related to the moderator tem-perature coefficient.

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4.6 Maintain steam generator and feedwater conditions as stable as possible as natural circulation develops.

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' i - G p_ 2 Page 4 of 12 l

4 lQ Y

g' I/d INITIALS /DATE

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4.7 Minimize thermal shock on the pressurizer spray nozzle by initiating spray slowly and maintaining a minimum con-tinuous flow once spray is actuated.

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4.8 00 not irse auxiliary spray if letdown is isolated.

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4.9 If a reactor trip occurs during natural circulation, close the spray valves (RC-PCV-455A and B) and restart Reactor

. Coolant Pump RC-P-1C prior to closing the reactor trip breakers. p m7

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4.10 Refer to the manual trip criteria listed in Attachment 9.3.

Insure that these criteria are available in the control room for operator reference. /

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4.11 Maintain CS-V177 (Loop 4 alternate charging path) in the

(,

" CLOSED" position throughout the test.

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4.12 Charging flow should be constant and at as low a flow rate q,

as possible during this test.

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A 5.0 INITIAL CONDITIONS d

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5.1 Reacter power is approximately 3% witn rod control in N

" MANUAL".

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5.2 All reactor coolant pumps are operating.-

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5.3 Steam dump is operating in the pressure control mode and maintaining cold leg temperature at approximately 557'F in manual control.

2

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5.4 The Station computer is operating.

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5.5 Pressurizer pressure control and level control are in manual and maintaining pressurizer pressure at approxima-tely 2235 psig and level at 25% (range 25 to 30).

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5.6 The startup feedwater pump is maintaining steam generator levels at approximately 50% (40-60%) narrow range, through the bypass valves.

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5.7 RCS boron concentration and control bank red positions are configured to establish an approximately zero moderator temperature coefficient. Control Banks should be arranged so that there is at least 150 pcm of inserted red worth.

c..e.e. ses.y. cer-

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5.8 The steam generator atmospheric relief valves are avail-able for use as necessary.

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5.9 Secure steam generator blowdown during primary calort-metric test activities.

- -. a 1-ST-22 Rev. 2 Page 5 of 12 2NITIALG/DATE

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5.10 Start the GETARS data recording for the paramaters iden-tified by Attachment 9.4.

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5.11 Picce analog points identified by Attachment 9.5 in a pro-cess computer block trend with a one-minute interval.

l 5.12. Place the following analog points in a process computer block trend with a one-minute trend interval.

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5.12.1 A0301, Reactor Coolant Loop 1 Flow.

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5.12.2 A0304, Reactor Coolant Loop 2 Flow.

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5.12.3 A0307, Reactor Coolant Loop 3 Flow.

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5.12.4 A0309, Reactor Coolant Loop 4 Flow.

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5.13 Close, or verify closed, CS-V177 (alternate charging path) and open, or verify open, CS-V180 (normal charging path).

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S.14 Perform, or verify the performance of, each intermediate and power range channel and P-7 interlock analog channel operational test within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating startup and physics tests.

Document this review in chronological log.

(This will satisfy Technical Specification Surveillance Requirement 4.10.4.1.)

6.0 TEST INSTRUCTIONS q

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6.1 Perform Reactor Coolant System heat balance per Attachment <.,

9.1.

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6.2 Obtain Intermediate Range Detector Normalization constants determined by ST-16. Calculate Intermediate Range current limits to limit power to 5% per Attachment 9.8, and record on Attachment 9.3.

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.3

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6.3 During the performance of this test, ST-22, the thermal 1

~

power shall be determined to be less than P-7 interlock setpoint at least once per hour. The logging of power h

level will be performed on Attachment 9.9.

See Special j

Precaution 4.1.

(This will satisfy Technical i

Specification Surveillance Requirement 4.10.4.1.)

J

/

6.4 Obtain a core thermocouple (T/C) map at approximately three (3) minute intervals using the Station computer until the end of the stt.,ilization period and continue as directed by the test director.

Insure each map is appropriately labeled with the test number, step number, date, time and initials of the person performing the cata collection.

1-ST-22 Rev. 2

~

Page 6 of 12 TNITIALS/DATE l

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6.5 Perform, at approximately ten.(10) minute intervals, sub-cooling monitor performance test as directed in Attachment 9.2.

This subccoling monitoring will continue throughout the test unless otherwise directed by the test director, or as specified within the test. Coordinate data collec-tion with T/C map data recording.

6.6 Natural Circulation

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6.6.1 Simultaneously trip all reactor coolant pumps.

Annotate GETARS and MPC trends and record the time NOTE:

1) The steam generator levels may shrink slightly before swelling.

2) Expected RCS response is listed in Attachment 9.3, along with the manual trip criteria.

/

6.6.2 Place Spray Valve Controllers RC-PK-455B and

.[ j RC-PK-455C in " MANUAL", and open (fully) Spray Val _ves RC-PCV-455A and RC-PCV-4558.

(Ope'rging

((#

these valves will attow auxiliary spray flow to go to loops 1 and 3, anc.' closir; these valves will direct auxiliary spray flow to the pressurizer.)

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6.6.3 Adjust charging ficw and letdown flow, as reqdred to maintain cer.stant RCS water mass. Maintain pressurizer level control in ' MANUAL'.

NOTE:

Pressurizer level can be expected to increase slightly over 1 percent per degree Fahrenheit change in RCS average temperature. Do not allow pressurizer level to increase above 607..

NOTE:

Steps 6.6.4 and 6.6.5 can be reper.ted, as required to control pressurizer pressure at the direction of the test director.

CAUTION: MINIMIZE SPRAY N0ZZLE THERMAL SHOCK BY INITIATIN SPRAY FLOW SLOWLY AND MAINTAINING SPRAY FLUID AT TO LESS THAN 320*F.

/

6.6.4 If pressurizer pressure exceeds 2260 psig, open Auxiliary Spray Valve CS-V185. Manipulate CS-V185, RC-PCV-455A and RC-PCV-4558, as necessary, to maintain approximately 2260 psig.

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6.6.5 If pressurizer pressure exceeds 2290 psig, close charging line valve, CS-VISO, and manually throttle close Spray Valves RC-PCV-455A and RC-PCV-4558, as required to maintain pressurizer pressure at approximately 2260 psig.

n 1-ST-22 Rev. 2 Page 7 of 12 INITIALS /DATE

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6.6.6 Maintain the plant at stable conditions while natural circulation stabilizes.

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6.6.7 Natural circulation should take from 10 to 50 1

• minutes to stabilize. Verify plant conditions approximating the conditions below are observed. i Note characteristics in the chronolog.

a.

Constant AT between wide range hot cnd cold leg temperatures.

b.

Constant AT between wide range cold leg tem-parature and core exit T/C temperature.

c.

Wide range hot leg temperature is approxima- $b--

tely equal to core exit T/C average tempera-ture.

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6.6.8 Annotate GETARS and Station computer trends when stable natural circulation is achieved. Record the time and continue recording data for d minimum of thirty minutes.

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6.6.9 Collect data for Attachment 9.1, Page 3.

6.7 Auxiliary Spray Depressurization Rate Demonstration

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6.7.1 Verify, or adjust as required, so that pressurizer pressure is between 2225 and 2260 psig, and that pressurizer level is stable.

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6.7.2 Continue to obtain core thermocouple maps approxi-mately every five minutes and start data trending equipment, as required.

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6.7.3 Place the Pressurizer Backup Heater Groups A, B, C and 0 control switches to the "0FF" position.

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6.7.4 Place or verify the pressurizer control heater group control switch is in "AUT0" position.

NOTE:

Maintain an accurate log (chronological log) of position of Charging Line Valve CS-V180 and Spray Controllers RC-PK-4558 and RC-PK-455C.

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6.7.5 Open, or verify open, Auxiliary Spray Valve CS-V185.

If pressure cannot be maintained below 2260 psig with CS-V180 open, mark N/A for Steps 6.7.6 - 6.7.7 and go to Step 6.7.8.

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JNITIALS/DATE CAUTION: MINIMIZE SPRAY N0ZZLE THERMAL SHOCK BY INITIATING SPRAY FLOW SLOWLY AND MAINTAIN SPRAY FLUID AT TO LESS THAN 320'F.

/-

6.7.6 dpen, or verify open, CS-V180, and observe pressure response for at least fifteen minutes.

Five minutes into the observation period, close Spray Valve RC-PCV-455A. When RC-PCV-455A is shut, close RC-PCV-4558, as possible (see note).

Annotate GETARS and MPC trends.

NOTE:

Do not allow pressurizer pressure to drop below approximately 2000 psig.

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6.7.7 Open Spray Valves RC-PCV-455A and RC-PCV-4558, and close CS-V180. Allow pressure to recover to a value greater than 2100 psig and stabilize.

Annotate GETARS and MPC trends.

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6.7.8 Close RC-PCV-455A and RC-PCV-4558 and observe the pressurizer pressure response. Annotate the GETARS and Station computer trends.

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6.7.9

. Position RC-PCV-455A, RC-PCV-4558, CS-V180 and the pressurizer heater controls, as required, to sta-bilize pressurizer pressure at approximately 2050 psig. Annotate GETARS and MPC trends.

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6.7.10 Perform a subcooling monitor performance check as directed in Attachment 9.2.

6.8 Charging and Steam Flow Effect on Subcooling

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6.8.1 Start data trending if stopped and annotate the trends with date, time and section.

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6.8.Z Increase pressure and stabilize at approximately 2200 psig using RC-PCV-455A, RC-PCV-4558, CS-VISO and the pressurizer heaters as required. Reduce pressurizer spray flow to a minimum so that charging flow to the RCS loop is maximized.

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6.8.3 Perform a subcooling monitor performance check as directed in Attachment 9.2.

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6.8.4 Note current charging flow rate (

gpm) and increase charging flow by approximately 15 gpm.

Stabilize the charging flow, then perform a sub-cooling monitor check (AttacNnent 9.2).

Allow approximately 15 minutes to elapse before continuing.

(Record actual charging flow rate in the chronolog.)

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1-ST-22 Rev. 2 Page 9 of 12 INITIALS /DATE

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6.8.5 Increase charging flow an additional 15 gpm.

Stabilize the charging flow, then perform a sub-cooling monitor check.

(Attachment 9.2) Allow approximately 15 minutes to elapse before

• continuing.

(Record actual charging flow rate in

'the chronolog.)

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6.8.6 Reduce charging flow and lower pressurizer level as required. Balance charging and letdown flow rates.

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6.8.7 Use the pressurizer heaters to stabilize RCS pressure at approximately 2235 psig, then perform a subcooling monitor performance check.

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6.8.8 Carefully increase steam dump flow until the RCS average cold leg temperature has decreased by approximately 5"F.

Avoid an excessive increase in stemn flow.

NOTE:

The 5'F increase in saturation margin is desired, but is not required for test acceptance. Do not decrease cold leg temperature below 550*F.

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6.8.9 Perform a final subcooling monitor performance check. Obtain the final T/C maps.

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6.8.10 Place all pressurizer heater controls in "AUT0" with a 2235 psig setpoint.

6.9 Loss of Pressurizer Heaters During Natural Circulation

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6.9.1 Open, or verify open, the normal charging supply valve, CS-V180, and close, or verify closed, Auxiliary Spray Valve CS-V185.

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6.9.2 Start the GETARS and MPCS data trending groups identified in Steps 5.10 and 5.11, as required.

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6.9.3 After approximately ten (10) minutes, secure all pressurizer heaters. Backup heaters to "0FF",

control group to "0FF".

Record time and annotate GETARS and MPCS data trenes, as appropriate.

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6.9.4 Mark the pressurizer pressure recorder, RC-PR-455, to denote the start of RCS pressure reduction.

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6.9.5 Continue to acquire data until one of the following conditions is reached:

m_

1-ST-22 Rev. 2 Page 10 of 12

)

INITIALS /DATE a) RCS Tavg below 541"F (any WR Tave).

b)

Pressur1rer pressure below 2050 psig (by lowest sensor),

c) Pressurizer heaters must be used for any reaso d) Reactor coolant pumps are started due to unplanned or unexpected equipment conditions.

e) One hour (60 minutes) has elapsed.

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6.9.6 Mark the pressurizer pressure recorder, RC-PR-455, to denote the end of data acquisition.

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6.9.7 Return the pressurizer heater control switches to the configuration desired by the Unit Shift Supervisor. Record the time

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6.9.8 Stop the GETARS and MPCS data trending groups.

Remove MPC trend from logger and mark with test number, date, time and step sequence. Additional data collection may be desired, and it is at the discretion of the test director to continue data collection.

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6.10 Plant Restoration

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6.10.1 Shut down the reactor by fully inserting the control banks and log the mode change.

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6.10.2 Fully insert the shutdown rods.

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6.10.3 Open the reactor trip breakers.

Upon opening the breakers, notify I&C to perform 151680.950, P-4 voltage testing.

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6.10.4 Open, or verify open, the normal charging valve, CS-V180, and close, or verify closed, Auxiliary Spray Valve CS-V-185.

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6.10.5 Place pressurizer spray c~o'n' trollers PK-455B and PK-455C in

• MANUAL / CLOSED". Operate pressurizer heaters as required to maintain RCS pressurizer at approximately 2235 psig.

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6.10.6 When wide range AT is less than 5'F and pressuri-zer level is stable at 25 to 30 percent, restart Reactor Coolant Pump RC-P-1C in accordance with Station operating procedures.

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6.10.7 After pressurizer pressure has stabilized, return Pressurizer Spray Controllers RC-PK-455B and RC-PK-455C to "AUT0".

/

UNITED STATES

[

NUCLEAR REGULATORY COMMISSION j

REQlON i Q

f 475 ALLENDALE ROAD u,,e

. KtNG OF PRUSSIA. PENNSYLVANIA 19406 Docket No. 50-443 Public Service Company of New Hampshire ATTN:

Mr. Edward A. Brown, President and Chief Executive Officer New Hampshire Yankee Division Post Office Box.300 Seabrook, New Hampshire 03874 Gentlemen:

Subject:

NRC EVALUATION OF SEABROOK STATION, UNIT 1, OPERATOR PROFICIENCY In a conversation on September 7, 1989, between Mr. Joseph Grillo, Unit 1 Operations, and Mr. Peter Eselgroth, Chief, PWR Section, arrangements were mcde for an NRC evaluation of operator proficiency.

The NRC is planning to conduct the evaluation of all shift operating crews on the Seabrook Unit 1 simulator, using NRC-developed scenarios during the week of December 11, 1989.

The scenarios will cover various types of broad evolu-tion / transients ar.d will not be limited to the use of the E0Ps.

In order for the NRC staff to adequately develop scenarios for the evaluation, it will be necessary for you to furnish the reference material listed in Attach-ment 1 by October II, 1989. Also, we will need one simulator instructor and one operations person to assist in the validation of the simulator scenarios developed by the NRC.

The two individuals will be required to sign a security agreement that they will not knowingly divulge the scenario contents to other facility personnel and not be involved in further training of the operators after validation of the scenario contents.

Future communications will confirm the schedule and finalize our needs.

Your cooperation with us in this matter is appreciated.

If you have any ques-tions concerning this matter, please contact Mr. Peter Eselgroth, of my staff, at 215-337-5211.

Sincerely, 1

Robert M. Gal o, Chief

%$hD Operations Branch j

Division of Reactor Safety J

SEP 228 MucLEAR sgEN W EXHIBIT 2 j

l

-__--_-_-_--_--__---__--_-___A

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.Public Service Company of New Hampshire 2 CC:

J.'C. Duffett, President and Chief Executive Officer, PSNH T. C. Feigenbaum, Senior Vice President and Chief Operating Officer, NHY J. M.. Peschel, Operational Programs Manager, NHY D. E. Moody, Station Manager, NHY l;

T. Harpster, Director of* Licensing Services l-J. Grillo, Operations Manager P. Richardson, Training Manager

- P. W. Agnes, Jr.., Assistant Secretary of Public Safety, Commonwealth of Massachusetts Public Document Room (PDR)'

Local Public Document Room (LPDR)

Nuclear Safety Information Center (NSIC)

NRC Resident Inspector

-State of New Hampshire Commonwealth of Massachusetts Seabrook Hearing Service List-

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REFERENCE MATERIAL REQUIREMENTS FOR z.

SEABROOK STATION, UNIT 1 OPERATOR ASSESSMENTS 1.

Operator training material on Seabrook Unit I plant systems.

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2.

All integrated plant procedures (normal or general operating procedures).

3.

All emergency procedures (emergency instructions, abnormal or special procedures), including bases, if applicable.

4.

Conduct of operations administrative procedures.

5.

All annunciator / alarm procedures.

6.

Emergency plan implementing procedures.

7.

Technical specifications.

8.

System.operatir.g procedures.

9.

Piping and instrumentation diagrams and electri:a1 single-line diagrams.

10.

Simulator malfunction book.

11.

List of all preprogrammed initial conditions.

12.

Copy of simulator scenarios used by the facility to train on the 20Ps.

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' UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY AND LICENSING BOARD Before the Administrative Judges:

((g.,,

/,

IM m Ivan W.

Smith, Chairman Dr. Richard.F. Cole Kenneth A. McCollom

)

In the Matter of

)

Docket Nos. 50-443-OL

)

50-444-OL PUBLIC SERVICE COMPANY

)

(Off-Site EP)

'OF NEW HAMPSHIRE, EI AL.

)

)

-(Seabrook Station, Units 1 and 2)

)

September 22, 1989

_)

CfJTIFICATE OF SERVICE I,

John Traficonte, hereby certify that on September E2, 1989. 1 made service of the within INTERVENERS' SECOND INFORMATIONAL SUPPLEMENT TO THEIR LOW-POWER CONTENTIONS FILED ON JULT 21 AND AUGUST 28, 1989 by Federal Express as indicated with (*) and by first clans mail to:

• Ivan W.

Smith, Chairman

• Kenneth A. McCollom Atomic Safety & Licensing Board 1107 W.

Knapp St.

U.S.-Nuclear Regulatory Stillwater, OK 74075 Commission East West Towers Building

• Docketing and Service 4350 East West Highway U.S. Nuclear Regulatory Bethesda, MD 20814 Commission Washington, DC 20555

• Dr.

Richard F. Cole Paul McEachern, Esq.

l Atomic Safety & Licensing Board Shaines & McEachern l

U.S.

Nuclear Regulatory Commission 25 Maplewood Avenue East West Towers Building P. O. Box 360 i

'4350 East West Highway Portsmouth, NH 03801 Bethesda, MD 20B14 l

• Robert R.

Pierce, Esq.

• Thomas G. Dignan, Jr.,

Esq.

Atomic Safety & Licensing. Board Katherine Selleck, Esq.

-U.S.

Nuclear Regulatory Commission Ropes & Gray East West Towers Building One International Place 4350 East West Highway Boston, MA 02110 Bethesda, MD 20814 H.

Joseph Flynn, Esq.

• Sherwin E. Turk, Esq.

Assistant General Counsel U.S. Nuclear Regulatory Office of General Counsel Commission Federal Emergency Management Office of the General Counsel Agency 15th Floor 500 C Street, S.W.

11555 Rockville Pike

. Washington, DC 20472 Rockville, MD 20852 Atomic Safety & Licensing Robert A. Backus, Esq.

. Appeal Board Backus, Meyer & Solomon U.S.

Nuclear Regulatory 116 Lowell Street Commission P.O.

Box 516 Washington, DC 20555 Manchester, NH 03106 Atomic Safety & Licensing Board Jane Doughty U.S. Nuclear Regulatory Commission Seacoast Anti-Pollution League Washington, DC 20555 5 Market Street Portsmouth, NH 03801 Charles P.

Graham, Esq.

Barbara St. Andre, Esq.

Murphy & Graham Kopelman & Paige, P.C.

33 Low Street 77 Franklin Street Newburyport,1%

01950 Boston, MA 02110 Judith H. Mizner, Esq.

R. Scott Hill-Whilton, Esq.

79 State Street Lagoulis, Hill-Whilton 2nd Floor

& Rotondi Newburyport, MA 01950 79 State Street Newburyport, MA 01950 Dianne Curran, Esq.

Ashod N. Amirian, Esq.

Harmon, Curran, & Towsley 145 South Main Street Suite 430 P.O.

Box.38 2001 S Street, N.W.

Bradford, MA 01835 Washington, DC 20008 l

l Senator Gordon J. Humphrey Senator Gordon J..Humphrey U.S. Senate One Eagle Square, Suite 507 Washington, DC 20510 Concord, NH 03301 (Attn: Tom Burack)

(Attn: Herb Boynton) _________________

J

1 1

l John P. Arnold, Attorney General Phillip Ahrens, Esq.

Office of the Attorney General Assistant Attorney General 25 Capitol Street Department of the Attorney Concord, NH 03301 General Augusta, ME 04333 William S. Lord Board of Selectmen Town Hall - Friend Street Amesbury, MA 01913 l

l COMMONWEALTH OF MASSACHUSETTS 1

JAMES M.

SHANNON ATTORNEY GENERAL fEc-L p'hn Traficonte ghief, Nuclear Safety Unit

/ Department of the Attorney General

' One Ashburton Place Boston, MA 02108-1698 (617) 727-2200 DATED:

September 22, 1989 I

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