ML20248D386
| ML20248D386 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 09/28/1989 |
| From: | Traficonte J MASSACHUSETTS, COMMONWEALTH OF |
| To: | Atomic Safety and Licensing Board Panel |
| References | |
| CON-#489-9240 OL, NUDOCS 8910040233 | |
| Download: ML20248D386 (23) | |
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION
'eg SEP 29 N0 55 ATOMIC SAFETY AND LICENSING BOARD Before the Administrative Judgea: [
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 28, 1989
)
MOTION FOR RECONSIDERATION The Massachusetts Attorney General (" Mass AG") moves that this Board reconsider its Memorandum and Order (" Unauthorized Pleadings")
(" Order") dated September 26, 1989, which:
1) determined that the Interveners' Second Informational Supplement ("Second Supplement") dated September 22, 1989 was an unauthorized pleading; 2) found that the Second Supplement (and the documents attached thereto) "need not be considered further," (Order at 2; and 3) excused all parties from responding to " pleadings that fail to satisfy, in inIm and substance, the Commission's pleading requirements unless the Board invites such responses."
(Order at 2.)
In support of his motion for reconsideration, the Mass AG states:
8910040233 890928 PDR ADOCK 05000443 G
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'I 1.
-The Second Supplement was filed for the purpose of incorporating-two documents (Exhibit 1 and Exhibit 2) received on September 22, 1989 by the Mass AG into the low-power-contentions and bases filed on July 21 and August'28, 1989, i
- The Mass AG did not (and did not intend to) amend the bases of I
l those~ earlier. filed contentions with Exhibit 1 except'to the extent that references in those contentions and bases to the
" procedures" for the Natural Circulation Test would now be understood to-be references to the actual procedures document I
l l
not received by the Mass AG until September 22, 1989.
For j
example, in the August Contention Statement (attached as-
-Exhibit 1 to the Interveners' August 28 filing) there are
~
i statements referencing the Startup Test Procedure for the Natural Circulation Test.
(Sag, e.g.,
JI-LP-1 Basis F, 11 at 1, 15 at 5; Basis G, 11 at 10; JI-LP-2 Basis A at 16; JI-LP-3 i
Basis B at 19; Basis D at 23.)
Had the Mass AG been in possession of the Startup Test Procedure for the Natural l
Circulation Test on August 28, he would have attached the l
i document to that earlier filing and made reference specifically I
to it.
Upon receiving it on September 22, the Mass AG (acting in light of his obligations under NRC practice) l l
1/
In. keeping with those selfsame obligations, the Mass AG j
agein submits the Startup Test Procedure and moves that it be 1
associated with his August 28 and July 21 filings.
Again, the present intent is not to " amend" those filings except to l
incorporate this document.
Obviously, the Mass AG has had this document since September 22 and is filing it (again) on September 28.
In defense of this delayed filing, the Mass AG 1
states:
- 1) He did not receive it until September 22; and 2) He
{
did not anticipate that the Board would treat its filing as 1
" functionally a late-filed contention" (Order at 1), strike it and, thus, require this effort to submit it a second time, still within four business days after its receipt.. I
- p promptly filed the document as " additional support" for those
' earlier filings.
2.
The Second Supplement did not address all the requirements of $2.714(a)(1)(i-iv) or $2.734 because the Mass AG did not consider Exhibit 1 to rise to the level either of a new late-filed contention or an amended basis to contentions already, filed.A#
Instead, as discussed, it was viewed as a document not.available earlier, that supplemented that earlier filing which.Interve.nors had.an nblication in. time _ly file upon receipt if. they hDp_ed in have i_t consideJ.etd by thia RaaI_d in decidina in' admit their low-power testina contentions.
The Second Supplement.did state at 1.that the Mass AG had received the' document on September 22, 1989 pursuant to a FOlA request.
Had the Mass AG understood that the Board would demand that the requirements of SS2.714(a)(1)(i-iv) and 2.734 be addressed in L
these circumstances, he would have proceeded in one of two ways:
a)
The Mass AG would have titled the Second Supplement differently (calling it a " Motion to Add Supplementary Documents") and then set out in that motion the discussion above, incorporating by reference those portions of the July 21 and August 29 filings that address the late-filed contention and record reopening standards; or b)
The Mass AG would have filed the entire July and August pleadings again verbatim incorporating the document and editing the pleadings to refer to it.
2/
As review of Interveners' August 28 filing makes clear (August 28 Motion at 12-19), the Mass AG did address those standards in seeking to add bases to his July filing. _ _ - - _ - _ _ _ _ _ _ _ - _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ - _ __
- e; t
3.
The analysis of Exhibit 2 -- the NRC's September 15 notification of further operator testing -- is substantially similar.A For example, in the August 28 Motion at 17-18, Interveners assert that "the Staff stated that these issues
[ low-power events] are safety _significant" referring to certain Staff actions.
Exhibit 2 was submitted for the purpose of adding cupport to this claim by making' clear that the Staff has taken further actions E.ubsequent to the Auoust 28 filina whish' LIntervenors want this Board to consider in reachina its decision concernino the admissibility of Interveners' low-oower Contentions.
As noted, had the Interveners understood that this Board would require a repetition of Interveners' arguments on late-filed and reopening ctandards (either by incorporation or by resubmission) they would have provided such.A' 4.
The Mass AG is unclear on how to proceed in order to protect his and other Interveners' rights to a public hearing on all issues material to the granting of a full-power license to the Seabrook Applicants.E#
1/
For the same reasons and on the same basis set forth in footnote 1 above the Mass AG again submits herewith Exhibit 2 to the Second Supplement.
A/
Other than stating when the two documents were received, Interveners had (and have) nothing to add to their discussions of these standards already set forth in the July and August filings and in their September 1 Reply to the responses of the Applicants and Staff to their July motione 5/
The Mass AG has sought a schedule for the filing of both low-power testing contentions and contentions that may be generated by the September 27, 1989 onsite exercise.
Absent l
Board guidance, Interveners must file their materiels in a series af pleadinas if aRd AE nRCessary to meet the timeliness requirements pressed repeatedly by the Applicants and Staff and to ensure sufficient basis and specificity. l
c ;s:
.Inllight'of.the above discussion, the Mass AG on. behalf'of al'l-Interveners,Emoves that this Board' reconsider its September 26fOrder and' accept-the attached Exhibits as-documentary supplements to.the July'and August' low-power testing
. filings.E#
l' Respectfully submitted, COMMONWEALTH OF MASSACHUSETTS JAMES M.
SHANNON ATTORNEY GENERAL
~
hn Traficohte hief, Nuclear Safety Unit epartment of the Attorney General One Ashburton Place s
Boston, MA 02108-1698 (617) 727-2200 DATED:
September 28, 1989 6/.The Mass AG also requests clarification regarding whether any other Intervenor pleadings have been effectively stricken as a result of and in light of the September 26 Order.
(The Order at I refers to the Second Supplement as an " example" of an " unauthorized pleading'.)
If so, the Mass AG would seek to timely resubmit any information or documents that this Board has stricken. >
-_._-..__.__________.m
m
. ji
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s DOCKETED-UNITED STATES OF. AMERICA NUCLEAR REGULATORY COMMISSION
-ATOMIC SAFETY AND' LICENSING BOARD' Before the Administrative Judges:
Ivan W.
Smith,' Chairman Dr.. Richard F. Cole Kenneth A. McCollom 1
)
In the-Matter of
)
Docket Nos. 50-443-OL
)
50-444-OL PUBLIC SERVICE COMPANY
).
(Off-Site EP)
OF NEW HAMPSHIRE, EI AL.
)
s
)'
-(Se6 brook Station, Units.l.and.2)
)
September 28, 1989
)
CERTIFICATE OF SERVICE I,
John Traficonte,-hereby certify that on September 28, 1989, I made service of the within MOTION FOR RECONSIDERATION by Federal
. Express as indicated with (*) and by first class 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 l*
Bethesda, MD 20814 Commission l
l Washington, DC 20555
- Dr. Richard F. Cole Paul'McEachern, Esq.
Atomic Safety & Licensing Board Shaines & McEachern U.S.-Nuclear Regulatory Commission 25 Maplewood Avenue East West Towers Building P. O.
Box 360 4350 East West Highway Portsmouth, NH 03801 Bethesda, MD 20814 i
a
- 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 Cc;cnission 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, MA 01950 Boston, MA 02110 Judith H. Mizner, Esq.
R.
Scott Hill-Whilton, Esq.
79 State Street Lagoulis, Hill-Khilton 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 Senator Gordon J.
Humphrey Senator Gordon J.
Humphrey U.S.
Senate One Eagle Square, Suite 507 Washington, DC 20510 Concord, NH P3301 (Attn: Tom Burack)
(Attn: Herb Boynton) l 1 1
1
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 COMMONWEALTH OF MASSACHUSETTS JAMES M.
SHANNON ATTORNEY GENERAL 1
f*
//
./J hn Traficonte hief, Nuclear Safety Unit
[
Department of the Attorney General One Ashburton Place Boston, MA 02108-1690 (617) 727-2200 DATED:
September 28, 1989 l _. _ _ _ _ _ _ _ _ _ _ _ _ _
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- 14
- Appendix B STPD Rev. 2
- Form 1 SEABROCK STATION Startup Test Procedure 1 -ST-22 Rev.
___2
Title:
NATURAL CIRCULATION TEST Prepared by:
R. A. Gwinn Date:
J/SO/W DETERMINATION OF 10CFR50.59 APPLICABILITY:
1.
Does this procedure or revision:
\\
a.
Make changes in the facility As described l
IYes IXlNo in the FSAR?
b.
Make changes in procedures ac described I
lYes l X l No
~
in the FSAR?
c.
Involve tests or experiments not described l
lYes l X l No in the FSAR?
d.
Involve changes to the existing Operating l
lYes l X l No License or require additional license requirements?
2.
If any of the above questions are answered m, a safety evaluation per NHY Frocedure 11210 is required.
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Approval Reconraended by:
5tartup Manager
' D&te Approved:
I D
Station en Date Soer a 84 55 cxaran i
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1-ST-22 Rev. 2 Page 1 of 12 SEADR00K STATION STARTUP TEST PROCEDURE 1-ST-22 NATURAL CIRCULATION TEST Prepared by:
R. A. Gwinn SECTION TITLE PAGE 1.0 08JECTIVE 2
2.0 REFERENCES
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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1-ST-22 Rev. 2 Page 2 of 12 1.0 CBJECTIVE This test will determine 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; depraasurization rate following loss of pressurizer heaters; depressurization rate using auxiliary spray; effect of charging flow and steam flow on subcooling margin; succooling monitor performance.
2.0 REFERENCES
CURRENT NO.
TITLE REVISION REVISION 2.1 1-ST-1. Startue Program Administration 2
2.2 Seabrook Station Technical Specifications Amend 1 Precautions Limitations anc Setpotnts for 2.3 the Westinghouse NSSS 2
Se&Drook Station F5AR, RAI Responsa 2.4 640.51-4t 56 2.5 ES-0.2. Natural Circulation Cooldown 6
2.6 ASME Steam Tables 5th Ed.
Seacrook Station F5AR, Table 14.2-5, 2.7 Item 22 knend 61 2.8 Startuo Test Procram Description 2
INITIALS /DATE 3.0 PREREQUISITES
/
3.1 The test. director has reviewed the latest revisions of the app 11cabia references to determine if any system changes that have been made will affect the test performance.
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3.2 Personnel involved with the performance of this procedure have been briefed on the procedure content and infT med 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 items which cay restrict the performance of the test.
/
3.4 Instrument inputs to GETARS is arranged to include those identified by Attachment 9.4, as a minimum, and at a scan i
rate of less than or equal to 250 millisecond interval.
l
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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.
7_
,a.e m c _
3
_,_ __.ma-2_ _n e &d 1-57-22 Rev. 2 Page 3 of 12 INITIALS /DATE 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
- Servire Air.
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3.6.3 Instrument Air.
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3.6.4 Circulating Water System.
l
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3.6.5 Main Condenser.
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3.6.6 Chemical and Voltane Control System (including 1
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 that as many Operations personnel as possible mayiwitness the test. (See Reference 2.4.)
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3.8 The Unit Shift Supervisor has been notified that the test is about to conmence.
4.0 SPECIAL PRECAUTIONS
,,3, g,,,) Q,9 3.to.3
/
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4.1 The requirements of Technical Specifications 3.4.1.1 or 3.10.4 and the associated surveillance requirements must be aohered to throughout the performance of this test.
/
4.2 Do not exceed 5'/ thermal power at any t.ime during this test.
l
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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.
/
4.4 Cold leg temperature should be maintained at approximately the initial (pre-RCP trip) temperature.or greater than 550*F unless otherwise directed.
1
/
4.5 All personnel participating in the test should be aware that the moderator temperature coefficient is near zero and may change sign during the test. This is to reduce reactivity feedback effects related to the moderator tem-perature coefficient.
/
4.6 Maintain steam generator and feedwater conditions as stable as possible as natural circulation develops.
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N 1-ST-22 Rev. 2
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k INITIALS /DATE 2.
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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.
Do not 5se auxiliary spray if letdown is isolated.
/
4.8
/
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-IC prior to closing the reactor trip breakers. p wt,
/
4.10 Refer to the manual trip criteria listed in Attachment 9.3.
Insure that these criteria are available in the controi room for operator reference. /
/
4.11 Maintain CS-V177 (Loop 4 alternate charging path) in the
(,
" CLOSED' position throughout the test.
/
4.12 Charging flow should be constant and at as low a flow rate as possible during this test.
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+
5.0 INITIAL CONDITIONS O
s
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5.1 Reactor power is approximately 3% with rod control in N O
" 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.
1
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5.4 The Station computer is cperating.
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5.5 Pressurizer pressure control and level control are in Jmanu 1 and maintaining pressurizer pressure at approxima-tely 2235 psig and level at 25% (range 25 to 30).
/
5.6 The startup feedwater pump is maintaining steam generator levels at approximately 50% (40-60%) narrow range, through the bypass valves.
/
5.7 RCS boren concentration and control bank rod 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, cos.< see-y. err
/
5.8 The steam generator atmospheric relief valves are avail-able for use as necessary.
/
5.9 Secure steam generator blowdown during primary calort-metric test activities.
e
--_A e
1-ST-22 Rev. 2
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Page 5 of 12 INITIALS /DATE
/
5.10 Start the GETARS data recording for the paramaters iden-tified by Attachment 9.s.
/
5.11 Place analog points identified by Attachment 9.5 in a pro-cess computer block trend with a one-minute interval.
5.12 Place the following analog points in a process computer clock trend with a one-minute trend interval.
/
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 cpen, or verify open, CS-V180 (normal charging path).
/
5.14 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
/
S.1 Perform Reactor Coolant System heat balance per Attachment 9.1.
> g. x,. :3,c 7
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6.2 Obtain Intermediate Range Detector Normalization constants determined by ST-16. Calculate latermediate Range current limits to limit power to 5% per Attachment 9.8, and record on Attachment 9.3.
17 3
/
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 i
Precaution 4.1.
(This will satisfy Technical 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 untti the end of the stabilization 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 data collection.
.I 1-57-22 Rev. 2 Page 6 of 12 INITIALS /DATE
/
6.5 Perform, at approximately ten (10) minute intervals, sub-cooling monitor performance test as directed in Attachment 9.2.
This subcooling monitoring will continue throughout the test unless otherwise directed by the test director, or as specified within the test. Coordinate data collet-tion with T/C map data recording.
6.6 Natural Circulation
/
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 RC-PK-455C in " MANUAL", and open (fully) Spray Valves RC-PCV-455A and RC-PCV-4555.
(Opeqing
.((q these valves will allow auxiliary spray flow to go to loops 1 and 3, and closing these valves will direct auxiliary spray flow to the pressurizer.)
/
6.6.3 Adjust charging flow and letdown flow, as required to maintain constant 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 60%.
l NOTE:
Steps 6.6.4 and 6.6.5 can be repeated, as required l
to control pressurizer pressure at the direction l
of the test director.
~
CAUTION: MINIMIZE SPRAY N0ZILE 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.
/
6.6.5
.If pressurizer pressure exceeds 2290 psig, close charging line valve, CS-V180, and manually throttle close Spray Valves RC-PCV-455A and RC-PCV-4558, as required-to maintain pressurizer pressure at approximately 2260 psig.
l
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1 1-5T-22 Rev. 2 Page 7 of 12 l
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 circt.lation should take from 10 to 50 f
minutes to stabilize. Verify plant conditions approximating the conditions below are observed.
Note characteristics in the chronolog.
a.
Constant AT between,ide range hot and cold leg temperatures.
b.
Constant AT between wide range cold leg tem-perature 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.
/
6.6.8 Annotata GETARS and Station computer trends when stable natural circulation is achieved. Record the time and continue recording data for d minimum of thirty minutes.
/
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 pt essurizer 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 f!ve minutes and start data trending equipment, as required.
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6.7.3 Place the Pressurizer Backup Heater Groups A, 8. C and D control switches to the "0FF" position.
/
6.7.4 Place or verify the pressurizer control heater group control switch is in "AUT0" position.
NOTE:
Maintain an accurate log (chronological leg) of posttion of Charging Line Valve CS-V180 and Spray Controllers RC-PK-4558 and RC-PK-455C.
/
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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1-ST-22 Rev. 2 Page 8 of 12 I
INITIALS /DATE
)
i CAUTION: MINIMIZE SPRAY N0ZZLE THERMAL SHOCK PY INITIATING SPRAY FLOW SLOWLY AND MAINTAIN SPRAY FLUID AT TO LESS THAN 320*F.
i
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6.7.6 dpen, or verify open, CS-V180, and cbserve 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.
7,.,,.*-
/
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.
/
6.7.8 Close RC-PCV-455A and RC-PCV-4558 and observe the pressurizer pressure respense. Annotate the GETARS and Station computer trends.
/
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 IETARS and MPC trends.
/
6.7.10 Perform a subcooling monitor performance check as dirr;cted in Attachment 9.2.
6.8 Chargino &nd Steam Flow Effect on Stbcooling
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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 97e uure 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.
/
6.8.3 Perform a subcooling monitor performance check as directed in Attachment 9.2.
/
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 (Attachment 9.2).
Allow approximately 15 minutes to elapse before continuing.
(Record actual charging flow rate in the chronolog.)
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.)
'/
6.8.6 Reduce charging flow and icwer pressurizer level
~
as required. Balance charging and letdown flow rates.
/
6.8.7 Use the pressurizer heaters to stabilize RCS pressure at approximately 2235 psig, then perform a subcooling monitor performance check.
/
6.8.8 Carefully increase steam dump flow until the RCS average cold leg temperature has decreased by approximately 5'F.
Avoid an P.xcessive increase in steam 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.
/
6.8.9 Perform a final subcooling monitor performance check. Obtain the final T/C maps.
/
6.8.10 Place all pressurizer heater controls in "AUT0" with a 2235 psig catpoint.
6.9 Loss of Pressurizer Heaters During Natural Circulation
/
6.9.1 Open, or verify open, the normal charging supply valve, CS-V180, and close, or verify closed, Auxiliary Spray Valve CS-V185.
/
6.9.2 Start the GETARS and MPCS data trending groups identified in Steps 5.10 and 5.11, as required.
/
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 trenos, as appropriate.
/
6.9.4 Mark the pressurizer pressure recorder, RC-PR-455, to denote the start of RCS pressure reduction.
/
6.9.5 Continue to acquire data until one of the following conditions is reached:
L ~ -4 c_
L L
1-ST-22 Rev. 2
-Page 10 of 12 U
INITIALS /DATE
- /
/
a) RCS Tavo below 541*F (any WR Tave).
b) Pressurizer 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.
/
6.9.6 Mark the pressurizer pressure recorder, RC-PR-455, to denote the end of data acquisition.
/
6.9.7 Return the pressurizer heater control switches to the configuration desired by the Unit Shift Supervisor. Record the time
/
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.
\\
6.10 Plant Restoration
/
6.10.1 Shut down the reactor by fully inserting the contrcl banks and log the mode change.
/
6.10.2 Fully insert the shutdown rods.
/
6.10.3 Open the reactor trip breakers. Upon opentry the breakers, notify I&C to perform 151680.950, P-4 voltage testing.
M
/
6.10.4 Open, or verify open, the normal charging valve, CS-V180, and close, or verify closed. Auxiliary a
Spray Valve CS-Y-185.
/
6.10.5 Place pressurizit'r spray cbn' trollers PK-455B and PK-455C in ' MANUAL / CLOSED". Operate pressurizer heaters as required to maintain RCS pressurizer at approximately 2235 psig.
/
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.
/
6.10.7 After pressurizer pressure has stabilized, return Pressurizer Spray Controllers RC-PKd558 and RC-PK-455C to "AUT0".
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UNITED STATES t
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O NUCLEAR REGULATORY COMMIS$10N REQlON I
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47s ALLENDALE ROAD KING OF PRUS$tA. PENNSYLVANIA 19404 SEP10'pveg Occket 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 Operatiens, and Mr Peter Eselgroth, Chief, PWR Section, arrangements were made for an NRC evaluation of operator proficiency.
The NRC is planning to conduct the evaluation of all shift operating crews on the Seabrook Unit I simulator, using NRC-developed scenarios during the week of December 11, 1989.
The scenarios will cover various types of broad evolu-tion / transients and 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 11, 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-tnat 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 confinn 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
, Chief
@ENED 0,e,ation, e,,nch Division of Reactor Safety NUCLEAR W k
EXHIBIT 2 1
l
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av 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 T. Harpster, Director of Licensing Services J. Grillo, 0:erations 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
---.__m_
L REFERENCE MATERIAL REQUIREMENTS FOR l
SEABROOK STATION, UNIT 1
-OPERATOR ASSESSMENTS 1
1.
Operator traini'3 material on Seabrook Unit 1 plant systems.
~
2.
All integrated plant procedures (normal or general operating l
procedures).
l 3.
All emergency procedures (emergency instructions, abnormal or special procedures), including' bases, if applicable.
/
Conduct of operations administrative procedures.
5.
All annunciator / alarm procedures.
6.
Emergency plan implementing procedures.
7..
Technical specifications.
8.
System operating procedures.
9.
piping and instrumentation diagrams and electrical 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 E0Ps.
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