Text

Requests Removal of Listed Address from NRC Mailing List for All Documents Excepts for Documents Prepared Per Natl Environ Policy Act for Projects in New England States
	ML20248J419
Person / Time
Site:	Pilgrim, Seabrook, Vermont Yankee, Yankee Rowe, Maine Yankee
Issue date:	07/09/1991
From:	Higgins E; ENVIRONMENTAL PROTECTION AGENCY
To:	; Office of Nuclear Reactor Regulation
References
	NUDOCS 9107150339
	Download: ML20248J419 (11)
	v • d • e

(.

~ _ - -.. _

j 5

-jglo tte 6

UNITED STATES ENVIRONMENTAL PROTECTION AGENCY-y REGION I J F. KENNEDY FEDERAL BUILDING BOSTON, MASSACHUSETTS 022034211

,y July 9, 1991 office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Dear Sir /Madrut I am writing to request that you remove the following address from your mailing list for all documentes except for thoso prepared pursuhnt to the National Environmental Policy Act for

. projects in New England statest l

EIS Review Coordinator

-EPA Region I JFP. Federal Building B3ston, MA 02203 Current:1y, NRC sends to that address numerous unnecessary documents, such as Monthly Operating Reports, for nucicar power plants in New England (Vermont Yankee--Docket No. 50-271; Pilgrim--Docket No. 50-293; Maine Yankee--Docket No. 50-309; Seabrook, Unit-1--Docket No. 50-443; Yankee Atomic--Docket No.50-029).

The most'recent mailing:is enclosed'.

I would appreciate your making sure these no longer get sont to the above address.

Thanks very much.

Sincerely, 9

'1 M

( h61 k[

/l[W [fliMT/q Elizabeth Higgin k ongram

(.

Assistant Director Office of Environmental Review t

i i

m\\' f-i p

-91071gggy h,f[ Nc9

-q,,

nea eda i

- m e. c. cme..

l-

/y. sung %

UNITED STATES i

NUCLEAR REGULATORY COMMISSION E'

W ALHIN010N, D C. 205t,b n

i i

June 28, 1991

%,..... /

00ckti N0(St 50-029 Els Review Coordinator EPA Region 1 JFK Federal Building Boston, Massachusetts 02203

SUBJECT:

YAhKEE ATOMIC ELECTRIC COMPAt1Y - YANKEE ATOMIC POWER STAT 10ft The following dntuments concerning our rt view of the suotect f acility ate transmitted for your information E _

._ _.. DESCRIPJON OE D00VMENT__...

.. DATED _ _

Notice of Receipt of Application Draf t: Final Enviror. mental Statement Notice of Availability of Draft Final Environmental Statement Safety Evaluation Report, or Supplement No.

Environmenta! Assessment and finding of No Significant Impact Notice of Issuance of Environmental Assessment Notice of Consideration of Issuance of Facility Operating License or Amendment to f acility Operating License Biweekly Notice; Applications and Amendments to Operating Licenses inyp]ying Np_S!gnjtippnLHal#ros.Cun@ttons._

See Papeisk Es emption Construction Permit No, CPPR-

. Amendment No.

(

Facility Operating License No.

Amendment No.

Order Monthly Opciating Report for N07 I N

X

__ transmitted by Letter Annual /SemeAnnual Report:

transmitted by Letter Other Office of Nuclear Reactor Regulation

[nclosures:

As Stated with enclosure ec:

see next page

i t

fANKEE ATOMIC ELECTRIC COMPAlly 2

with enclosuri:

C5ief, Of vision of Ecological Servi:es fureau of $Dort Fisheries ( 'ti'411fg

'J. 5. Oeeartrent of tne Intecier lasningt n, 3. C. 20210 Or. Willian Canninghan

'3A 2esearen Chemist Bur?au of 3tandards & Technology Desctor Pailding 235. Poon B 108 Gaitnersburg. va ryland 20999 e

I o

YANKEE ATOMIC ELECTRIC COMPANY

"%)'j

g'* *l" y.

O S80 Main Street, Bolton, Massachusetts 01740a398 YANKEIE June 10, 1991 BYR 91-073 United States 11uclear Regulatory Commission Document Control Desk l

Washington, D.C.

20555 j

Dear Sir:

Submitted herewith is a revised nonthly Statistical Report for the Yankee Atomic Power Station for the month of May, 1991.

Very truly yours, YAtlKEE ATOMIC ELECTRIC COMPAllY 7.'h '

R.

L.

Berry Assistant to Vice President-operations RLB/gbc l

Enclosure c:

Region I Resident Inspector - Y11PS

$3((7 Sl . 1 !_d[--

910'5 r.l e

t PDR ADOCi 05000024 R

PDr, l.

a

- - - +

+-.----

m)yr..e y-

--a se

-c-a w<

-,wmm-

-ee-e--,

.em e

w

-swr-en-

s. -

l l

t u

YANKEE ATOMIC NUCLEAR POWER STATION MONTHLY STATISTICAL REPORT 91-05

(-

FOR-THE MONTH OF MAY, 1991 1

i l

1 s

l I

5

.,,.-....,s...,_.__,-.4.

,,-c

i t

6 l

(TIRAllR$ til A REP;R1 00:11110. !:.!!

CAff 110101 (tu?tillD 11 H.tAttAR0 11tiPQi

(!!!) til lit 1 CflRAlikt 11 Alt!

1.

Etithatt: YttttiR:st 2.

Rt;;ttiy Partet: i;ttl,1911 1.

llettst! ittrial h!r (Wit):

(CD 4.

natt:latt R:ttti (Ct:ss vit):

1!!

testi: lit:tfital Ratty (kti Viti:

ti!

t, Raitt;t Ot:sti::lt C :::ity (Cr:ss #st): It!

1.

N:it:;t Ot;ttt:tts C:* : tty (ht! Fit):

11 :U ;s (! tts 4::st 3 thr:.;*, ?! !!::: L:st Rt;;tt, Oht Pt:s:ts:

R If tt: tits 0:::t it 01;::

1.

P:sttttval1;thi:6.Ptstri:tti. Ifity(ht: Pet):.................................................................

it. Rt:s:t.s f:t Restri:ti;t:. If Ar,y:

1tts7:ttt it.t:f:tt

(.f;1:tus

?ti.;0 3,122.00

11. k:.ts In Rt;;tttt; Pct::t 714.00 1,(?!.;;

21!,7!!.11 1

12. L::tt ;f r:;ts Pt::::t 1:s tt ti::

0.00 C.t3 t.t:

13. Rts;t:t Ristivt it':ti:st. H:;ts 144.!:

3,511.!!

21h3!!.10 C.::

LOC 0.t ti. h:;'s tt.trat:t On-litt

11. tt: n 1*ttt:1 ittfly ttttratti (F:0 420,?i!.ll 2.!(1,lli.00 11!,2!!,ill.12

15. t :t Ptserit $ht::=: P:;ts 127,;!!.40 124,120.4; 34,t!),1!!10

11. Ct:ss ilt:tri::1 itet;y Ceterstcf (m) 11!,it?.!!

!!t,114,1!

12,t:1,2!!.!!

1!. het !!t:trical it.triy Ott.tt:tti (m) 100.00 19.34 18.!5 1:0,00 11.14 11.!!

11. toit ! rvi:t Ft:::t

!!,11 11!!

14.t

20. Vait At1111:111ty Fa:t:"

21. Uttt C::::1ty Ft:t:t (Vstig P: htt) 11.21

!!.it itt2 22, Unit t::a:lty it:tt.t (tsit.; til htt) t.!

0it 4.11

!! catt F;t::: ht:;t tats

24. tt;t::::s !:tt:;1t Citt hatt i N:ntts (Ty;t, Catt, att htatt:a :f 12:t):

D!

D b..

.5

.O Ik

..b%

1

, L,,,. l,. n.,.

1,.,.,i f

..r.

i d

l in!FA;ItitLYti!1P:lltl!Vl!

t;ttiik0. 10 !!

(1 11 iAull R:al CA11 litt:1 t:0LillttY H. tintt;;

it!!PKni

(!!!) ill lill X;n1H Ray,1991 CAY Attti;!tA!LYP;i!RtiVIL CAV IVl'A;l CA!!Y P: lit LI1tl (yttkit) tytt kil) 1 111.6 11 110.I 2

111.1 110.5 1

111.1 Il lit.:

1 111.!

ll 110.!

171.1 21 lit I

til.!

22 111.3 7

111.1 23 lit.l t

171.!

24 Ill.1 1

172.5 2!

1l1.1 1;

172.!

1!4 11 til!

2'

!!!.1 12 111.1 l!

121.1 13 til.1 21 123 14 1!1.1 3

10.2 1!

11 1.0 ll 4i.4 it 112.1 Ik!1P";1:lk!

tr. this f:rt:1, list ttt attt:;a ::'.ly stit :atr 't'.t1 it ytt \\tt f:t t::t : y it the tc;; rte; r:*.tt.

.tt 1 tti ttartst it:lt rti: nit.

l

i s

L'h!1 !N'Jit th! n0 F0fil F10','tillk!

t;;tilhl, it 2) l thlt YAktilR;il FIP;tiW;hlW Nay,Illt till 110111 (CWilltif L !AttAF;;

it![Fh;kt

(!!!)1191111 Rtit:0 Littt:tt C:;; tit:rtt:ttv 1

tet:ti:t 2 Of Itettit; tvtti lystts C:;:ttti 1;titt1:

k:,

tatt ty;t (h:;ts) Ft::n C:st Itt:t:r 1 Rt;;ft I (::t i b:t i Frtstat A ::fritti 11/07 t!/10 F

4!.i A

h/A t/A t/A h/A C:tittstr 16tt Lt:t, All ltaktti16ttsPl6;;t!.

1 1

4 f: f;r::

Rt:s:t, Nett::-

!stittt G !*stt;:ttes

!: !:tt:.it:

A!:r:rtttF:tlsts(b;1st) 14r;:1 f;rFrt;:f::1:t fCn:

14 ittttp:t : Itu

tr;:1 luar

[ttry !tttts f:t Lt: stat

Ftf;tlu; 1 W.:::':: tet,:

htu Rt::tt lLlR) Ftit 0Rt;;1:t:tritait:::':-

4 Ottu !b;i:14 iM Rt; ttt) i 0;ttn:' 'rttit; 1 !!:tt;t: !ilett::::1 F A:ratnint,t

1 sf i

00lt(1k0. IC !!

tt!!

IW!!10:1 Call I!!!Cl C0xPlil!DIf H.$Autitto fillPW;ki (Ill)f!!1111

!!PORIR; tin tay,1991 (LUAlf CF OP!R11!k3 IXPit!!i !!

1y 20, till. Its platt its c;tratti at i flis:tf testf Ittti if ttf Fly !Ith (El 10 lltvitt! Ict! tit:tf t!Gfts !!ysti ty Wlffit43 flyifttltitfit phtf StatiCA CG! lit. AtC21!C3

% 10th 4 ICA: flis:llin til [ttf0ftt! 13 C:f,t;tt t :: tit *:lf Itat star d att tttt plgjjiti.

l l

I

ys UNITED STATES g o %q%

NUCLEAR REGULATORY COMMISSION g

WASHINGTON, D C. 20$66

L June 28, 1991 g%,..../

DOCKET NOISI.

50-271 EIS Review Coordinator EPA Region 1 JFK Federal Building Boston, Massachusetts 02203

SUBJECT:

VERMONT YANKEE NUCLEAR POWER CORPORATION - VERMONT YANKEE NUCLEAR POWER STATION The following documents concerning our review of the subsett f acility are transmitted for yout infot* nation

.f_.

DESCRIPUON QE_ DOCUMENT

_ DATED _

Notice of Receipt of Application i

Draf t/ final Environmental Statement Notice of Availability of Draf t' final Environmerital Statement Safety Evaluation Report, or Supplement No.

Environmental Assessment and finding of No Signihcant Impact Notice of issuance of Environmental Assessment Notice of Consideration of Issuance of f acility Operating License or Amendment to facihty Operating Ucense Btweekly Notipe; Applications and Amendments to Operating Licenses 0Ypiv0L g_p!gnicanL%ardtCondtti.gns See Pagels)_ _ _

N 1

Exemption Construction Permit No. CPPR-

_, Amendment No.

facility Operating License No.

, Amendment No.

Order x

Monthly Operdting Report for 35y_}991

. transmitted by letter 6/10/91

/vinual/ Semi-Annual Report:

transmitted by Letter Other Ofhce of Nuclear Reactor Regulation inclosures:

As Stated oc:

with enclosure see next page

/!a%'t? d'ME! DOWER C04PCAA7 :tl 2

Chief. Division of Ecological Service-Bureau of Soort Fisheries & Wildlife U. S. Deeart.~ent of the Interior 1d5hington D. C. 20240 Dr. William Cunninga am FOA Desearch chemist 3sreau Of Standards 5 Technole;y Deset:r Sailding 235, 3:en B.1;8

'iaiteersburg "aryland 2:399 l

i l

4

'VEltMONT YANKliE NucLEAn POwlilt CORPORATION f'?'x_,

. j'= ' }. / ')

)

P O Box 157. Governot Hunt Road f ', ',' gIy)

Vernon. Vermont 05354-0157

- 'y (602) 257 7711 3)5,... )

June 10, 1991 VYV-91-134 U.S. Nuc. lear Regulatory Commission ATTH: Document Control Dock Wa shirigton, D.C.

20555 Dear Sir Submitted herewith is the Monthly Statistical Report for the Vermont Yankee Nuclear Power Station for the month of May, 1991.

V ry truly yours, VERI N YANFEE i C, 'AR POP R CORP.

N'1 ' ~

untt.h h. 1%rp yr Senior Vi Preside Oe rations cci

1) USNRC Region I 475 Allendale Road King of Prussia, PA 19406

2) USNRC Resident Inspector, VYNPS DP 0411 Rev. 3 Page 1 of 1 g ue,Nw u. c w,,i G(f rrs e.DocF cc o W.1'1 p

F res fk

4, 4

e f

VERMollT YAliKEE IlUCLEAR POWER STAl'IOll MoliTIILY STATISTICAL REPORT 91-05 FOR Ti!E MoliTH OF MAY, 1991 DP 0411 Rev. 3 Page-1 of 1

OPERATING DATA REPORT DOCKET NO.

50-271 DATE 910610 COMPLETED BY G.A.

WALLIN TELEPHONE (802)257-7711 l

QPERATING STATUS

1. Unit Name Vermont Yankee

2. Reporting Period!

May NOTES:

3.

Liconced Thormal Power (MWt):1593.

4. 11ameplate Rating (Gross MWo):

EAR S. Design Electrical Rating (Not HWo):

514(oci 504fec)

6. Maximum Dependablo Capacity (Gross MWo):

ill

7. Maximum Dependablo Capacity (Not MWo):

19.4 8.

If changes, occur in capacity ratings (Items Number 3 through 7) sinco last report, give reasons:

N/A 9.

Power lovelfto which rostricted, if any(Not MWo):

N/A

10. Reasons for rostrictions, if any:

N/A This Month Yr-to-Dato Cumulative

11. Hours in Reporting Period 744.0Q_

3623.00 162143.00

12. Number of Hours Reactor was Critical 744.00_

3382.70 131571.33

13. Roactor Reservo Shutdown Hours 0.0Q_

0. 0.2 0 22

14. Hours Generator On-Line.

714.00 3343.25 128734.85

15. Unit-Reserve Shutdown Hours Ouag_

0.00 0.00

16. Gross Thormal Energy Generated (MWH) 1174091.50 1264259.50 190579564.50

17. Gross Electrical Energy Generated 391968.00 1769891.00 63517386.02

18. Not Electrical Energy Gonorated(MWH), 373118.00_ 1694612.00 _p0326582.00

19. Unit Servico Factor 100.00 92.28 78.51

20. Unit Availability Factor 100.00 92.28 78.51

21. Unit Capacity Factor (Using MDC Not) 99.50 92.61 73.05

22. Unit Capacity Factor (Using DER Not) 97.57 91.Q2 71.63

23. Unit Forced Outage Pate.

0.00 7.72 5.57

24. Shutdowns scheduled over r. ext 6 months (Type, Date, and Duration of Each!

N/A

25. If shut down at and of report period, estimated dato of startup: N/A

26. Units In Test Status (prior to commercial operation): N/A Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION VYDPF 0411.01 LP 0411 Rev. 3 Page 1 of 1 RT No. 13.F01.19F

AVERAGE DAILY Ul1IT POWER LEVEL DOCKET IJO.

50-271 Uli1T Vermont Yan) Leg DATE 910610 COMPLETED BY G.A.

WA14111 TELEPilollE 18021257-7711 MO!JTil May DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-14et)

(MWe-Het) 1.

393 17.

.509 2.

514 18.

509 3..

515 19.

478 4.

516 20.

506 5.

515 21, 505 6..

515 22, 504

-7.

515 23, 498 8.

515 24.

491 9.

516 25.

488 10, 515 26.

491 11.

515 27.

492 12, 515 28.

494 13.

514 29.

495 14.

511 30, 492 15.

511 31.

489

16. -

509 I!1STRUCTIONS:

-on this format, list the averago daily unit power level in MWE-Net for-each day in the reporting month.

Compute to the nearost whole megawatt.

VYDPF 0411.02 DP.0411 Rev. 3 Page 1 of 1 RT No.-13.F01.18V

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO 50-271 REPORT MONTH MAY UNIT NAME Versont Yanket DATE 910610 COMPLeibu BY G.A. Wallin TELEPHONE (8021257-7711_

1 2

3 No.

Date Type Duration Reason Method of License System Component Cause and Corrective (hours)

Shutting Event Code Code Action to Prevent Down Report #

4 5

Recurrence Reactor 91-Oc 910519 S

0.00 B,H*

N/A N/A RB CONROD Control rod exercising and weekly turbine surveillance followed by a rod pattern j

exchange.

3 Method:

4 Exhibit G-Instructions 5: Scheduled A-Equipment Failure (Explain) 1 - Manual for Preparation of Data 1

F: Forced 2 Reason:

2 - Manual Scram Entry Sheets for License B-Maintenance or Test 3 - Automatic Scram Event Report (LER) File C-Refueling 4 - Other (Explain)

(NUREG 0161)

D-Regulatory Restriction E-Operator Training and 5 Exhibit I - Same Source License Examination VYDPF 0411.03 F-Administrative DP 0411 Rev. 3 G-Operational Error (Explain)

Page 1 of 1

H-(Explain)- rod pattern exchange

I i.

DOCKET NO.

50-271 DATE 910610 j

COMPLETED BY Q.A. WALLIN 1

TELEPHONE (8021257-7711 i

REPORT MONTH MAY

SUMMARY

OP OPERATING EXPERIENCES Hichlinhts Vermont Yankoo operated at 29.1% of ratoo thermal power for the month.

Gross electrical generation was 391.968 MWHo or 97.6% design electrical capacity.

Onoratina summarv l

The following is a. chronological description of plant operations including other portinent items of interest for the month:

l At the_beginning.of the reporting period tl.a plant was operating-at 78.7%

.of rated thermal power.

910516 At 0001 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , began cooling tower operations and went to a hybrid cycle of operation.

Varying modos of cycle operation from this point on will be based upon river temperature considerations.

910519.At 0150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months , initiated a power reduction to loss than 80%

to perform a rod. pattern exchango.

(Sco Unit Shutdowns and Power Reductions) 910519 At 0340 hours0.00394 days 0.0944 hours 5.621693e-4 weeks 1.2937e-4 months , completed the rod pattern exchange.

910519 'At 0522 hours0.00604 days 0.145 hours 8.630952e-4 weeks 1.98621e-4 months , began a return to full poWor.

1 r

At the end of the reporting period the plant was operating at 29.9% of ratoo thermal power.

i VYDPF 0411.04 L

DP 0411 Rev.

3' I

Page 1 of 1 RT'Ho. 13.F01.18X

s' oce4 UNITED STATES f

NUCLEAR REGULATORY COMMISSION j

g WA$mNGTON. D C. 20$bt,

' t,

/

June 28, 1991 v..*

50-293 DOCKET NOIS).

EIS Review Coordinator EPA Region 1 JFK Federal Building Boston, Massachusetts 02203

SUBJECT:

BOSTON EDIS0N COMPANY - PILGRIM NUCLEAR POWER PLANT The following documents conteming our review of the subject f acility are transmitted for your information.

.x_

DESCRT110N_QEDQCVMENL

__DA.TE0_

Notien of Receipt of Application Draf t/ Final Environmental Statement Notice of Availabihty of Draft! Final Envnonmental Statement Safety Evaluation Report, or Supplement No.

Environmental Assessment and finding of No Significant impact Notice of issuance of Environmental Assessment Notice of Consideration of issuance of Fatihty Operating License or Amendment to f acility Operating License Biweekly Notge; Apphcations and Amendments to Operating Licenses Iriyp!ying3gygni gent HugtdLQqn@tions See Pay (s) f Exemption Construction Permit No. CPPR-Amendment No.

Facihty Operating License No.

, Amendment No.

Order x

Monthly Operating Report for Mg 1991 transm:tted by Letter 6/14/91 Annual / Semi-Annual Report:

transmitted by Letter X

Other Discharge Monitorina Report - May 1991 6/19/91 Office of Nuclear Reactor Regulation inClO$Uf C&:

As Stated cc: With enclosures see next page

m _. _ _ _ _.__

BOSTON EDISON COMPANY t.

Chief. Division of Ecological Service; Bureau of Sport Fisheries & Nildlife V, S. Department of the Interior Washington D. C. 20240 Dr. William Cunningham FDA Research Chemist Bureau of Standards & Technology Reactor Building 235. Room 9 108 Gaithersburg, Maryland 20899 l

i l '

i i

l x

- = - -,,_ _..._,,,._..i------,,,-;.-,...,

m

O 1

BOSTON EDISON hignm Nut var Ponet Station Rocky H+il Road h, mouth. tAassachusetts o2300 l

$.# No7IS" hr Ilv'c'fl.', o"lll$on, June 14,1991 BECo Ltr. #91-80 U.S. Nuclear Regulatory Commission Attention:

Document Control Desk Hashington, DC 20555 License No. DPR-35 Docket No. 50-293

Subject:

May 1991 Monthly Report

Dear Sir:

In accordance witii PNPS Technical Specification 6.9. A.2, a copy of the Operational Statb. Summary for Pilgrim Nuclear Power Station is attached for your information and planning.

Should you have any questions concerning this report please contact me directly.

R.A. Anderson \\

6

,)

HJH/bal Attachment cc: Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Rd.

King of Prussia, PA 19406 Senior Resident Inspector Jfp ' kbOF_j: 0500iI?"g3 7((#,

.,_910531

,.r.

I rs j1j fy l

AVERAGE DAILY _ UNIT POWER LEVEL DOCKET NO.

!ip-293 UNIT Pilorim 1 DATE June 14 1991 COMPLETED BY H. Hunto TELEPHONE (508) 747-8474 HONTH Hav 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HHe-Net)

(HHe-Net) 1 0

17 0

2 0

18 0

3 0

19 0

4 0

20 0

5 0

21 0

6 0

22 0

7 0

23 0

8 0

24 0

9 0

25 0

10 0

26 0

11 0

27 0

12 0

28 0

13 0

29 0

14 0

30 0

15 0

31 0

16 0

This format lists the average daily unit power level in HHe-Net for each day in the reporting month, computed to the nearest whole megawatt,

OPERATING DATA REPORT l

DOCKET NO.

50-293 DATE June 14. 1991 COMPLETED BY H. Hunto s

TELEPHONE

_1508) 747-8474 OPERATING STATUS Hotes 1.

Unit Name Pilarim 1 2.

Reporting Period Hav 1991 3.

Licensed Thermal Power (MHt) 1923 4.

Nameplate Rating (Gross HHe) _

655 678 5.

Design Electrical Rating (Net HHe) 6.

Maximum Dependable Capacity (Gross HHe)_._696 7.

Maximum Dependable Capacity (Net HHe) 670 8.

If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

None 9.

Power Level To Which Restricted, If Any (Net MHe)

None

10. Reasons For Restrictions, If Any N/A W

This Month Yr-to-Date Cumulative

11. Hours In Reporting Period 744.0 3623.0 161951.0

12. Number Of Hours Reactor Has Critical 0.0 2850.2 95450.9

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line 0.0 2850.2 91766.3

15. Unit Reserve Shutdown Hours 0.0 0.0 00

16. Gross Thermal Energy Generated (HHH) 0.0

_5276592.0 158618088.0

17. Gross Electrical Energv Generated (HHH) 0.0 1812180.,Q 53459694,0

18. Net Electrical Energy Generated (HHH) 00 1743822.0 513702302D 1

19. Unit Service Factor 0.D 78.7 56.7

20. Unit Availability Factor 0.0 78.7 56.7

21. Unit Capacity Factor (Using HDC Net) 0.0 71.8 47 3

22. Unit Capacity Factor (Using DER Net) 0.0 73.5 48.4

23. Unit Forced Outage Rate 100.0 3.6 12.5

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refuelina Outaae No. 8. aDoroximately 70 days

25. If Shut Down At End Of Report Period, Estimated Date of Startup 7/13/91 I

BOSTON EDISON. COMPANY PILGRIM NUCL' EAR POWER STATION DOCKET NO. 50-293 Ooerational Summary for Hav 1991 g-The unit started the reporting period in cold shutdown.

Refueling outage Number 8 commenced at 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on May 4, 1991.

i l

Safety Relief Valve Challenges Month of Hav 1991 l

Requirement: NUREG-0737 T.A.P. II.K.3.3 j

There were no safety relief valve challenges during this reporting period.

An SRV challenge is defined as anytime an SRV has received a signal to operate via reactor pressure, auto signal (ADS) or control switch (manual).

Ref. BECo ltr. #81-01 dated 01/05/81.

i

[

REFUELING INFORMATION The following refueling information is included in the Monthly Report as requested in an NRC letter to BECo, dated January 18, 1978:

5 For your convenience, the information supplied has been enumerated so that, each number corresponds to equivalent notation utilized in the request.

1.

The name of this facility is Pilgrim Nuclear Power Station, Docket Number 50-293.

2.

Scheduled date for next Refueling Shutdown: On or about April 1, 1993 3.

Scheduled date for restart following present refueling:

Third Quarter 1991 4.

Due to their similarity, requests 4, 5, & 6 are responded to collectively under #6.

5.

See #6.

6.

The new fuel loaded during the 1986/87 refueling outage was of the same design as loaded in the previous outage, and consisted of 192 assemblies.

7.

(a) There are no fuel assemblies in the core.

(b) There are 2068* fuel assemblies in the spent fuel pool.

8.

(a) The station is presently licensed to store 2320 spent fuel assemblies.

The actual usable spent fuel storage capacity is 2320 fuel assemblies.

(b) The planned spent fuel storage capacity is 2320 fuel assemblies.

9.

With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 832 fuel assemblies.

Includes 168 new fuel assemblies to support current refuel outage.

580 fuel assemblies in the spent fuel pool will be returned to the core for Cycle 9.

PILGRIM NUCLEAR P0HER STATION HAJOR SAFETY RELATED HAINTENANCE EUTFH COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ACTION TO ASSOCINfED PREVENT RECURRENCE LER Recirc-Loop "B" Pump Increase in End of useful Seals to be replaced Frequency of seal LER 91-007-00 ulatico P201B Drywell floor life of the in both A and B replacement under System sump leakage inner seal of Recirculation System review.

(RECIRC) rate to great-Recirculation pumps during RFO-8.

Refer to associated LER.

er than 5 gpm pump "B".

(F&MR 91-122}

Primary N/A False high re-Root Cause Following the first To be determined.

LER 91-008-00 Contain-actor water investigation two isolations, the ment signal caused ongoing.

isolation signal was Isolat-three auto-reset and the main steam ion Con-matic PCIS line (MSL) drain valve trol Group 1 Isola-and the main steam System tions.

(F&MRs isolation (MSIV) valves (PCIS)91-124, 91-125 were reopened, to facil-and 91-127) itate decay heat removal.

Following the third isol-ation, the isolation signal was reset and the MSL drain valve and the MSIVs were left closed, using the Res-idual Heat Removal Syster; for plant cooldown.

l

Y-

~

U' FIT SHUTDOHNS AND P0HER REDUCTIONS DOCKET NO. 50-293 f

NAME Pilarim 1 DATE June 14, 1991 COMPLETED BY H. Munro TELEPHONE (508) 747-8474 REPORT MONTH May 1991 METH00 0F LICENSE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTEg COMPQNENT ACTION TO PREVENT 3

RECURRENCE 3

REPORT #

CODE C00E 2

DOWN REACTOR l

NO.

DATE TYPEI (HOURS)

REASON 8 05/01/91 F

79.0 0

4 91-007-00 AD P Seal Seal failure on f

"B" Recirculation Pump.

(continuation)

Seal to be replaced.

8 05/04/91 S

665.0 C

4 N/A N/A N/A Refueling outage No. 8 l

(continuation) 9 l

i 1

2 2

3 4&S F-Forced A-Equip Failure F-Admin 1-Manual Exhibit F & H S-Sched B-Maint or Test G-Oper Error 2-Manual Scram Instructions for C-Refueling H-Other 3-Auto Scram Preparation of 4-Continued Data Entry Sheet D-Regulatory Restriction E-Operator Training 5-Reduced Load Licensee Event Report

& License Examination 9-Other (LER) File (NUREG-1022) f t

i.

4 BOSTON EDISON 25 Braintree Hill Office Park Braintree. Massachusetts 02184

'.s h'cfp$7.7 June 19. 1991 i

Nuclear Engineerino BECo 5.91-051 NPDES Program Operations Section (HCP)

Environmental Prote tion Agency P. O. Box 8127 Boston, MA 02114 Massachusetts Division of Water Pollution Control Lakeville Hospital Lakeville, MA 02347 DISCHARGE MONITORING REPORT

Dear Sirs:

Enclosed is the Discharge Monitoring Report for Pilgrim Nuclear Power Station (PNPS), NPDES Permit Number MA0003557 (Federal) and Number 359 (State),

The period covered by this report is May 1991.

/

l

,,g A wtt

.J Ha.gner RDA/ cab /4233 Attachments:

1. Summary

2. Discharge Monitoring Report cc: U. S. Nuclear Regulatory Commissiony' Document Control Desk Hashington, DC 20555 U. S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Senior NRC Resident Irispector Pilgrim Nuclear Power Station

/

g\\

7 o[>

[

- m e%2 m ioS31

/

ADOCK0500g;3 DR

e ATTACHMENT 1 TO BECO LETTER 5.91 051

SUMMARY

PILGRIM I DI.SCHARGE MONITORING REPORT In accordance with the Federal Clean Hater Act, as amended (33USC 1251 gi irg:

the "CHA"), and the Massachusetts Clean Hater Act, as amended (H.G.L.; Chap.

21, 26-53), regarding effluent limitations, monitoring requirementc and othar conditions set forth in the Pilgrim NPDES Permit (Federal Permit Number MA0003557, and State Permit Number 359), parts I and II, the following information is submitted for the period May 1991.

I.

Discharae Points Covered in this Report Discharae Point Discharae Identification 001 Condenser Cooling Hater 002 Thermal Backwash for Biofouling Control 003 Intake Screen Wash 004, 005, 006, and 007 Yard Drains (April and September) 010 Service Cooling Hater Oil Hakeup Hater and Demineralizer Haste Discharge II. Summary and Notes of Discharae Recort A.

The flow at points 001 and 010 are calculated from system pump capacity and are equal to the total for all pumps in each system running at full capacity for a 24-hour period.

The flow at point 011 is measured by noting sump levels before and after discharge.

Flow at point 002 is a conservative figure obtained by calculating flow if backwashing took place for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Flow at point 003 is calculated from system pump capacity and mean operating time.

B.

The temperatures at points 001 and 002 are measured by resistance temperature detectors (RTD's).

C.

Periodically, total residual chlorine (TRC) concentration in the service cooling water (010) exceeds Permit requirements (0.50 ppm daily average TRC and 1.00 ppm daily maximum TRC) prior to mixing with any other stream, primarily because of the number of service water pumps in operation.

Chlorine injection levels are lowered as a corrective measure.

The dilution provided by the PNPS circulating water flow keeps total residual chlorine concentrations discharged to Cape Cod Bay below the NPDES Permit limit of 0.1 ppm.

l

x

[

L D.

Intake traveling water screens were operated with dechlorination pumps operating at all times.

O E.

No sawdust was applied to seek and seal PNPS condenser leaks.

F.

The removal of approximately 100 cubic yards of sand from the concrete floor of the intake structure occurred from April 23-May 2, 1991.

It was pumped into breakwater crevices above the high tide mark.

The sand removal was necessary to alleviate concern over its effects on n cmal operation of mechanical components / traveling screens, and it was expected to have no adverse environmental impact.

G.

The Pilgrim Station 1991 Environmental Monitoring, Thermal Discharge Fish Surveillance, and Dissolved Nitrogen Saturation Reduction e

Program and Plans were approved by the USEPA on May 22, 1991 as being in conformante with the NPDES Permit #KA0003557 (BECo Letter 5.91.046).

H.

The Pilgrim Station NPDES Permit #KA 0003557 was nenewed for a five year period on April 29, 1991 (BECo Letter 5.91.037). Hay 1991 reporting is in conformance with discharge requirements and limitations of the new NPDES Permit.

I.

The following boron and sodium nitrite discharges (ppm) occured in May 1991 from discharge point #001. All discharges were below NPDES Permit limits prior to entering Cape Cod Bay.

Date Gallons Concentration Concentration Discharaed Discharaed Before Discharae Discharaed Boron 5/01/91 9,686

<0.05

<0.0001 5/15/91 9,352

<0.05 (0.0001 5/23/91 5,179 0.239 0.0003 5/28/91 5,511 0.199 0.0003 Sodium Nitrite 5/01/91 9,686 39.4 0.0508 5/15/91 9,352 31.8 0.0410 5/23/91 6,179 50.0 0.0645 5/28/91 5,511

<20.0

<0.0258

O ATTACHMENT 2 TO BECO LETTEk 5.91-051 DISCHARGE MONITORING RENRT I

eennesT tea se AMast.o wces (Indasta f*'*'7#8 */I***'** F 4/> **ft seATeo=*e. cottuvem7 eesensees stow mateen cretsen (NEDsf/

nanur__"E01I DL.f D_ U _E IL EE ULE LA MI_ _

CISCHAR93 840MITORINJ C.tPORT (DWR1 a ss; tirin MAJOR Form Approved.

^ *E H*RD CK Y_ tiI LL_R QA Q_ __._ _ _ _ _ __ _ _

MA0003557 001 1 (5U8R S )

OMB No. 2040-0004 RED _ U-

- ""' t E v" ** 2

- "~^***"'""*=a F - FINAL Approval expires 6-30-91.

_ _ _ ELI2!0MIB-.

_.__ _ _ _ _M JL Q 216 Q- -

COOLING WATERS mon Tom No Prmion L*C_LL_a n_ _

,,y Loc *TeoM raoM vi 03 Os To vi 03 3i

- - NO DISCHARGE I--l ***

ATTNa E.S.

KRAFT, PLANT MANAGER OAJh (JJJ1/ u -25f ame r184* uain NOTE: Reed inetnsctioso be8ere orwnpleting1No term.

O Card Oaty) QU ANYlTY OM LOADING (4 Card Osdr)

CU ALITY ON CONCENTRATION PARAMETER OS-JJ)

(SM )

US df)

(85 3J)

(J M )

,p g

...or,.e.

9AMQE

"#~87)

[\\

np e

AvEnAot M Axf M UM UNITS MINIMUM AVERASE M ARIM UM UNITS g g pg TEMPERATURE, WATER

. AMett

(

)

g~f

( 15)

O DEG. FAHRENHEIT by Nf 0

M 11 1

0 0

jin@Eb Mg hp39N k

9 E*

aTrQQW 1 OEG.F b M 9R f2b1 b*n[M$C EFFLUENT GROSS VALUEi

.-e h=--

4 1**e OXIDANTS, TOTAL

(

}

M EA.AM,tE

( 19)

O. M O o/jk G-2 DESIOUAL UaEMENT gjt 34044 1

0 0

1

% e W W hg"Nde 77m g

y Rg sung M ; Rag-2 EFFLUENT GROSS VALUE J

bNE

-_dM MG/L

$e $$$hvi kD FLOW, IN CONDUIT 07

. AM,t t

( 03)

(

)

28, f, 353.(

O 97/p9 ff MEA - EMENr THRU TREATMENT PLAN 1 50050 1

0 0

Pg' pf

$1MORg4'

{ D gJ k ' A T $*C.#

9 MtIm !sTInA R

y', U90$t bayE dBAff f RE MGD a3

.~

EFFLUENT GROSS VALUE WW SAMPLE MEASUREMENT l

0 5

~

. An.m t MEASUMEMENT I

.M-E M EASUREM ENT S A M PL E ME AGUREM ENT 1

+

l N AM2/ TITLE PRINCIPAL EXECUTlWE OFFICER e.CtwTrv useorm MoonLTv OF T>.g wePos.m to a7 a *eavt Ptmecenatte EmmaestD La TELEPHONE DATE a co mas p ann we mRTM naATutM Sute.rTYtD estatse.AND SASEO One nov evov.isov -oa-.SE.WWDvlDUALS 888EDAYtt.y eggpO esgLt.Tio.e OF T*eO FOS Osva o

T.e Yo e acurve Tw sue.vire g.t.amt.cwe= G ggf W44

/

04, O

wOa r

To u

.s.,.c.ut ACC.e MATEA8so COes.PLETE a Aas A

?>

T f

~.

- v7 a r L amt.,0.ea?.Mm w M e

Y e os.s w T.LYv.

ron o

e Or

.e..s.o o

o rw seeesuse eoo ano

. e -. -- -*--.~ d a-~ ~-a * --an* =a* * =, r

.t c,,

,,,cuy,y,

uu c ev.

e. -

Tveto og eniNTEo orr:CEn on AUTNonizRo AoENT NUM e ta vt a l Mo oAv CO*4 MENT AND EXPLAm AT80*e Or ANT vtOLATIONs ( Arference ed om haments here) e DH SHALL NOT VARY MORE THAN 0.5 PH STANDARD UNITS FROM INTAKE WATEP.

TAMP. SHALL AT i. O TIME EXCEED A 32 GEGREE RISE OVER TEMP OF INTAKE WATER.

EPAfctm 3320-1 (Rev. 9-48) Pr>6us ed/tions may be used, tetrLAcEs EPA roam v se weescos M Av soot st Usto.3 peon Or

etaMeTTer Nawaiacrmes9 (/=A.d*

natsan AL pettuve=T rnTwa Rej euMe=Aveem ever2es /RfDU)

FW Wamhawl MW1 CISCHARC3 htOMITORIN3 MEPORT (DW2/

f1AME BASION _.En 21_.P_II CdLIn_*_LARI._ _

a n>

nom MAJOR Form Appoved

**F **ELO CKY 58 Y L L_5L O10_. _ _ _ _ _ _ _ _ _._ _._.

MA000T%7 002 1 (5UBR S }

OMJ No.20404XAM.

etRM 7 nuweEn

=-a,==--""

F-FINAL Approvalexp!res 6 30 91.

ocn as _

CONDENSER BACKWASM R L IR Q111ti MA__0 M A CL--

MONITORING PERIOD T*

y1 u3 n

- - NO DI5 CHARGE 6 9 ***

i

~ ll,).yt~-~~=

~ ~ - - - - - ------

TEAR an o OAv vgAm MO DAY FA1**OI'*"-___""____________,_,___

Yl U.">

U1 NOTE: Read instructkme befors completing tNo ssem, ATTNs E.5.

KRAFT, PLANT MANAGER

<mo ma 94m am asa snj (J Card OniP) OU A hTiT f Oh LOADfMG (d Co.d Omdp)

CUALITY OR CONCENTR ATION

- - $8"C' S AM PLE NO.

PARAMETER (eg JJ)

(J44f) g Jg.JJ)

(eg.Jf)

(J,d.df)

TT**

u a

Aov...

AvgRAGE M ARIM UM UNITS WINIMUM AVERAGE M AXIMUM UNITS of.Jn i

TEMPERATUREr WATER s a M *Ls

(

)

( 15) g Nf og

""^*""*"

DEG. FAHRENHEIT i- -

j q;b*1 7..-

"g gg ;ggggg 1

[..

jl ' '

.: c 00011 1

0 0

f

-: peepese$j 4 rs ***

[

DEG,F t 02 4

EEEL UE rv i GROSS VALUE OWE

.O

.. e m d 4 *+**

SLOW, IN CONDUIT OP

.AMett

( 03)

C

)

THRU TREATMENT PLANT ME fyfM

""^*""'"'"'

%.i men MsTrna

.gm..

g agggggg g

e a***

saosa 1

o o

h 413CM O ' "

g JU @idR ? MINRM MGD Z**-

U

. #Jlh $$~E.._

i ****

FFFLUENT GROSS VALUP S AM PLE M EASU R EM ENT k * **

..M m f M E A S U R EM EN T s'

t

.A m E M EA GU REM ENT

/'l jf

.A m E M EASU REM ENT r

w -

~+1 e

u,w.,,

,.g l

}*

if

_g-S AN PL E M E AS U R EM ENT 4

t "]-k < ?} f *

~%i

h-1 neovesneneem rg.

-}

j%

y Q4gs\\p?

.h

. - Mitt e_

g3 g:+m 4

UNDE. et atfy or (me fmaY e.=aws armeo attv g ama.ed D TELEPNOME DATE

C.Oa. reverv N AM E /TITLk PRINCIPAL EIECUTIVE OFFICER ame Fam.st.eam a,rv.ev eu.oveu=.m S.u.e rfTED.agagesae o-s.o gano v.at o.ro a.eaYeo m

ou. v o

. emavvtv

. te <e o

-v a.c,cu.a vea, o. c,x rv e.<. vt fut.Sveeto.<r es.om.matiow e.. u s e i.co,uo.o 1

/

g f*.E

.FCs eaarom e MLe eur

[,

y or am.o.G v

a s

a.a e.rw-v v v

a

/&'A/VT-A4 gg

.5, c a,ur v

u.

at o

.ct

.a e

=

r.o. a.s.o sa

,=e

-ao n v

m s c.swvv. ~, _

,,,-. ~ f

.,,- o..=o a

,,oMATuRE Or wCie EnEcutivt or w os o.

*****"'*"#**""*'d***"*#""*'****d'"*'

OFFICER C# AUTMCRf2EO AGENT A,

NUM B EM YEAR MO CAY W

TYPED OR PRtNTkO CO*e.a E NT A ND EX PL a N

T ION OP A N Y w sOLa T ION S t A r.*eerare etJ e88.s a*. tars acre )

THF PH SHALL NOT VART MORE THAN 0.5 STANDADD UNITS FROM THAT OF THE INTAKE WATER. FLOW RATE IS TO BE ESTI uATED A5 IF RACKcLUSHING TOCK PLACE FOR 24 CONTINOUS HGURS. SEE PERMIT PAGE 7 FOR CONDITIONS EEGARDING TH l

t E@A#dM fM6 f tm6v. #s) OldcN:SN may de usea.

iages.Ac t s E. A roseM T.A. wa cN M Av aoT.E ustoa

,A.E OP

espses?T33 M Am siAoSecos (Imeduff Navesesa6 ++LowvassT pescis Amos toseesesavenes evamse (NPDES

- - f D #*

h*" 4IW1 DISCHIEOG ast!NITCCINs) E.EPO7.T (DwJt) a-isi urin MAJOR Form Approved.

sAus_"110110H_EQ_81_EILGEUi_ELARL _ _ __

^?f'.5 EE'RD CX L tiILI._ROA Q_ __ _ _ _ __ _ __ __ _.__

MA0003557 003 A (SUBR 5 )

OMJ No. 2040-0004.

- a"'r nUMiesse

.e.-a...-e....

p -- F IN A L Approvd eic>iree W91.

___ _ EED_11_ _ ____ _._._____ _ ___._____

Wm mm n2 P_LUtGUIH____ _ _._ _ _ff A_0216a.__

,E.,

o, uou,7anino,,,,oo rA.c_1prv 78 9e ua

.> i

- - NO DISCHARGE l_l ***

~~_--_______

,..R h**d'_L*"___________________._._

ya v>

vi NOTE: Reed Inseuetleen before somedettes tMe is:m.

ATTN-E S.

KRAFTr PLANT MANAGER oS21/ o2-2h 0429 as-20 us->w uasij

(, Card Omfp) QU ANTITY OR LOAotNe I(4 Card Omty)

GUALITY OR CONCdMTR ATIOM FatOUENCv g ag pgg NO.

PAR AN ETER (eg.Jf)

(344;)

l (jg43)

(4kgf)

(jg4fp a a P..e.

O rvr=

==

98 AX ted WM UNITS l

te tN;edule AVERAGE

(,w, AVERAoE M AXIM UM UNIT.

l

( 03)

- - - - (

)

/g

/e g

O

/ 6 FLOWr IN CONDUIT OR

. A na rts

"*^*"*'"""'

THRU TREATMENT PLANT 777gb cFF UENT G 05 VALUE HGD

.A.A ~.

UR. E 1;.

1 w.

MEASUREMENT

%mumMMM M6M N

MF*

A AS4PLE es E A SU R EM ENT Lash MM WM BHasiR38@KQMSGM M@N 4

.A-.

MEASUREMENT

.amr4@pg mgs lMnwWagesJ

~'

. E A ~.

l l

.URE..NT h hf h

k khfh hkb L

. A

_E MEASUREMENT h

h Y

h fh$h

~

TELEPHONE DA7E e CE*Yil'v truota pranativ or tsw taeaf e **ava ers--c ;.LLv s naaewego N AME/TtTLE PRINCIP AL EXECUTIvK OPPICER amo ame Faen4Leam untw voet esPassesaTeOne evenevYgo wepree a,ap easso 8"'

One aev sdousev OF T*eOSE esGvouaLS eMastceAYtt y arremeta com OWT apesseG Twf eneromemattO's a BE LG VE T*.E SUWa*fTED se#0s**ma reome f/f7

/7//WAbN 5.

'v* s esoNATURa Or e p cie i[EnEcuTivE IO'[/ 2kM

/

l

=

+,.o es,.,

,w. r., sm

^""^

wUweER vtAR wO oAv

.-.usC ees.----*--'da-e-~'--='*"ad**

OrPecER OR AUTNORizzo AcaNT TveEn On PR NTEo

'OMM E'NT AND EXPLAN ATION OF ANT vsOLATsONS (*ffere8Ke #dt ete chseessers ha s)

THE TEMPERATURF OF THIS DISCHARGE SHALL AT NO TIME EXCEED THE TEMPERATURE OF THE IHTAKE WAT Ja L L FISH SHELLFISH AND OTHER ORGANISM 5 COLLECTED 09 TRAPPED ON INTAKE SCREEN SHOULD ue--

aneuru, ne,untur m ur

' ' ' ' ' - ~

~

,A.E Or pKvehii93tM(Mov'. Maf Piwedf4d&& inPybirJaed'" * "" ' VrBL/tw A2 ironi. OJi%%M, Mr dE" uke'or

00179/910326-1057 1

i

,l!

~

M L

A,A g

V A

B A

gp= $

3 M.N D

H t

g a

g" 3

r n W "i

A M

g 4 U }f-O 1

e 9

e g

s T

O E

.e

}

.0 e

T 43 N

C.

7 Y

T D

A 0S t

N g

v.

i U

00s R

P

n A

s de

it e

Ai M M E

n t =

e0 r lp P

lI o

i e

Y w

e e A v4 p o0x I n'

. m #

l, l

. e

2. l O

h ]a E

M. gF e

CJ

-._ c

%Nv c

NE oa e

I r o

o d

3

)

s

~

M mBr Ee f

b T 9 L

O U

S gL oM p Gs M

M 7

N p

1

/

P

/

f FOA R n U

,, G i

L s

C 5

Ai

(, MC P

9 o

3 T.

Ha i(

1 i

T g

t 1

Qf 9

la w

Cr f'

Ag C

4 t

Se 3

) L Il M

a C

2

M 6

s T g

p U

3 a

t D d. Nf A

M y

C Og yE SN I g tR u

T T

1 N

I O"

TJ A

U A(

E A

9 N:

RRFU A5

N C

g, W

y C

M M

O gR G

OB I

T

/

E A

T M

S 7

JU- '

D O

Il 1

E /g E 3

[

A t M

p A gI R

g T

1 M(pI N

P i gR 0

O e'

f t

O f

v g

C 4M gV E

0 g

Il lal

/

LT k

j Ry t

f m

Og A

,i g

gN y

m U 3

gl a3 Y g.,,

R.

W f, A o.

u I

A

, n A

(j T (g v

r P 9

,A,D(i

g. O s

O 0 O

L D

R a

A 3

W E

l T

e A

u t m C

a.

, T r-O n.U U

n E

,Rr a.

s O

uC e

,,O

.e o lju 1

4

J N F A F N

a.

,P 0

i

,E n

.i e

7

}y

.t OP n

,R m

eO RS o

T M

lj t

i

)p U

r y

,S a (gg I

h[;

(l Og M

FU y

gM o

g M

8 G O

m N

8 dJ t

I

,t T

,O 4

ll L

aO UA w

D me

.R t

7 a

M

'A, o0a m

r(

1 I

l n

C j?

sfS DH

,O a

e A

E

{%

jj

.T o

i 4

g t

2 smm SL c.

t ee

,i 5

(

,ir l

,o n.

grt w

I o

nee 6 4 N

'g N

a

)

l om

,M M

c Ij S

t EO 7

3g D

+

p e

s,-

BI T

o sDv a

/

2 J

I 0

gf E

5 U

M J

N v

.Gu s

o'T u *'

T 5

a

.U I

U G

v 'e e A

s

,R-a Y A

(

M 3

r a

(

m e oAa m

0 i

jj S

t Let

' tu aSt AP O

N t

t O

M M%

M v.**

MO W

gH 0

i

/

t n

E ME P

/

D D a Sd

,C a

2 D

A v A

,S 0

f tea =e a

a

,I A

e eYm L

U

.D w

lj[

)

E

[

' ta s

s RJ M

+

TI OW

X Sea T 9 t

Lg*

c Il A

A SN ut a

Y(

r E e

Y t

,A M

t oat e

e v E r

_ - _L__

Q)

W %

O c

L De T

]

3 F

a s

c L

N s

A S

af w*

RF r

A tpO ei a.'

r a

U tac e

EV c

l sr oaO a

TP e m se f

mm h

=

= A U

~

tosa o

o

~

e C e 'E n WC y) 1 _ _

6 7

mj A E

t eru i

a f

n O

n.

L*

EY a

g v m,

2 d(

v e

e rtu t,

c e

r s

e CT Q

uvaC r

_ _ M_ _.G E

a a

s O C a II R C I _ _. _ _

A e

d

=G e

f l

A E

et r

VC e

s t

[

r U A s

A veu

?

u M._,M.

mm e

t EP e

mT T

T L

MM a

. A u

N v

N N

2_ _ _ _ _ _.

v sse e,d s SA b

N

.e E

E oog.,*

.M M

y t,.M

~.M n ""u '"

N C

a

R A

~

O F m

E 2._. _ _ _ __ M m

R R

M..

s OP s

M

~

M f

.U U

U U

g A

_ T a*

n

_ _ _. N k

C L

M R

^

.^

A

.A A

o S

O NU it u

G.

F E

E F

tv OP sd.

A M

M M

H UD _

O

. L E

1 E

v I

g s

E h

w P_ A LOA L

l A

o

. P URN U

W T M u

A O Q

W T

D F N( A E_

_ _ _ e A

L A

U

/ h ND E O r

. T VTP V

C T

I r P

L_ L A

A SUTJS f

N M

P j

s 'l F

L I

X

'It O ehD L S

s OD 8

e P T L.

R M

T SDN S

L A

LE E_ I. M s

9 A

R N HT K

T 3 o

O ONE O

P j

oMR t._1 D -_

T OM0R I

O A M

C O L CA

.v

.m a

.s " G Y L_ M P

M R

G_ C T G

I P X O

A s N

E

(

e

i. I. -

A SI S

R

(

r R

E 1

nWS C D I A

'f s

UT 0

5L NE1 T P

T D a

P T A NI 2 N

E t

s CS 2

DDfL

"_E f

3 NU E

T E

L A

NE 3

T W' '!L E R_ 2-T E'DS'*T S*

A D r

0U l

T I

m 7

T N

2 N

DI WU5L

/

TE r

E o

e T

IS OR0F e

NE f

sf M

J.

t M

e O

A a.M a **. E^ *':

XE LH0F A

n A

OR

' FT3 C N

O CL P

n^

C E

l l

PERMeTTEE M AMEp4DD9ges [fqMW N AfsOM AL POLLesTANT peacesames Russ**e ATson 999?Eas yfffDff/

ftAms. SIlilON_EILil_EILGR111 Pt AKl____

trief tit 191 MAJOR Form Approved.

I*W8"!I"'** F #@P**/

OffCHCO3 MONIT0%FM3 GEPOOT (DC/

e**l"*ILDC1Y HTlL_RQ10_ _ _ ___ _ _ _.__

MA0003557 011 A (5UBR S )

OMB No. 20400004.

F - FINAL Approval expires 6 30-91.

eEww T MumeEn

= = * * * * * =

___ __pFn 21.,_

MAKE UP WATER AND 3EMINERALIZE P_1.M011m

-.-- _ _ _.Jia._ Q 2 1ft0 _ _

you,7ag,go pggina a.=

8P ACB L81"r vgAn MS DAT TEAR MO OAV

'"a":

v1 U>

n

- - NO DISCHARGE l__l 1*S"'.L*"_______.___.___________

y1 9)

U1 NOTE: Reed instructione lue8ere completirig this form.

ATTN-E S-KRAFT, PLANT HANAGER W24 <22 3 Ixa (252n,2sa nam (J Card Omtp) OU ANTfTY OR LOADtMe (4 Card Omty)

OUALtTV OR CONCENTRAff0M

- ",,8=CT gguptg NO.

PARAMETER (dSJJ)

(144J)

(Jg (f)

(dg.Jf)

(Jd.4f)

==. AL ena AVERAGE M ARIM Utd UNITS M f MIM UM AVERAGE M AJt 9M UM UNITS

( 12)

(

)

d,g

7. 7 O O pA g[

PH

. AM cLE M Easu R EM ENT WCE# 4 LRAS Des @ Q, C"T, M' W -Of $

M@ $MN 9<

00400 1

0 G

y egeteep geebep WI[*1h-a

_6 SU ffN @

fiFUN M ****

i Er: FLUENT GROSS VALUE 4

( 19) 27' O gM M

(

)

SOLIDS, TOTAL sAMett j,,g

""^'""'"'"'

g-v'mE Ew_ d ggW g;;ii;ft g

acgp@agg,;.'

sUSPEhDED 3

p eepy

$ege4Iy g' ODb gi i

e manni i MG/L T

S'ATCM 00530 1

0 0

e EFFLUENT GROSS VALUE

( 03)

C

)

4 l

FLOW, IN CONDUIT 00 M EA.AM ett o.003 c.oto o

ES s

uREMENr THRU TREATMENT PLANT g

@ *****y y; y, &..

~@ m.apr.wsTInA 6, 0

r W..s.

e..* *.

w m

Os015v, n. 0.06R4 /A ;.

Q 50050 1

0 0

w I'

DISCMi t-g o,

f-F F F I IlF tJT GRO%S Va t IIF 2MBA* Addi o ' Ba INY MGO e,

x SAM PLE MEASUREMENT

^

l

^ ;

. AM E

MEAGUREMENT N

Whl eYh{ NOA : $

W$

Q

'[

~ Q

( U ' [.

,1 p.gnih9 f

h 'O,p,

bj. 4.

k M ft N

iT[L S AM PLE MEASUREMENT

'?3./

hjf '. *

[ --C a

5 5 hjy L.

. - 6. . ;

2k

.y,-

[

1 TN$'

x 2

S AM PL E MEASUREMENT

~

d 6 h.'.,

" ? r*, W Q.

!+

7 f

.s,.

g gg

,'(

j Aeguestesseret i :Lf}t. 7~

,ii.

-: 7 h;.gy M *-

k-TELEPHONE DATE s c<.svar unort ethatty or Law voca7 e esavt at m LT t a nssento s

N AME/ TITLE PRINCl*AL EXECUTUrE OFPRCER n..o ass raseg. nam wevee voc easFCateaTION Summerf'YtD **tetse AssO SASED one new susOurft* OF To eOSt ososwoouaLS namatcuattt e at S80pssasaL E F08D OWT A***eG Test sNFOpesa tss e atttwt Y*st S.JemerTTED **sFOpasavuose

*" ATu=E Or eR cat cuTivt

/

Q 4

esb Yout aCCtsmaTE A8sD Cons *ttTE e aae amant TMAT Tset et amt gaQ i

e.ssr eca.47..Pt m.ea.tv e s F o.t m s v.vissG F.t ~,St.E tausF08.Maavious. s,eCL,ucisco r se guen t 4L n o S c v.,w.

. es

., e,.,M,.o

.a u.c Oo a t

7 * ***O'***em.=a.

d h e OFFICER OR AUT MOR11E AGENT MUMBER YEAR MO DAV l

i A"

TYPED OR PRINTED

{

=8 m coM M E~T AMo Ex etANAnoM Or ANT v.ot. Tion. in n m m.u,n

- - a m,

FORMERLY DESIGNATED DISCHAPGE 0018. S A P8 P L E S T AK E *t IN COMPLIANCE WITH THE MONITORING REQUIREHENT5 3PECIFIE O ABOVE SHALL Bt TAKEN AT

f. POINT PRIOD TO pix!r.G WITH ANY OTHER STREAM.

enoE Or EPAform 3320-1 (Rev. 9-88) Previous ediflons may be used, teEPLActs EeA roRM T de wMecM MAv NOT eE UsRa.1

f[E*osc $%,

UNITED STATES o

NUCLEAR REGULATORY COMMISSION WASHINGTON. O C. 20$b5 y

g e

1 i

June 28,1991 l

%,..'../

DOCKET N0(S).

50-309 EIS Review Coordinator EPA Region !

JFK federal Building Boston, Massachusetts 02203 MAINE YANKEE ATOMIC POWER COMPANY - MAINE YANKEE ATOMIC POWER STATION

SUBJECT:

The iollowing documents concerni.ig our review of the subject f acihty are transmitted for your information.

2 DESCRMION_QF.. DOCUMENT

.__. D AT E D _

Notice of Receipt of Application Draft!Finat Environmental Statement Notice of Availability of Draf t! Final Environmental Statement Safety Evaluation Report, or Supplement No.

Environmentel Assessment and Finding of No Significant impact Notice of issuance of Environmental Assessment Notice of Consideration of Issaance of Facihty Operating License or Amendment to Facihty Ope:ating Licenso Biweekly Notice; Applications and Amendments to Operating Licenses

_l0Y9Lv10a_NQ SQntfgentliggrggfgndtttont _

See Pagejs) f Exemption Construction Permit No, CPPR-

. Amendment No.

Facihty Operating License No.

Amendment No.

Order Monthly Operating Report for _May_l.9.91_._.._.

transmitted by Letter 6/11/91 X

Annual l Semi-Annual Report:

j transmitted by Letter L%-

Office of Nuclear Reactor Regulation

Enclosures:

As Stated cc: with enclosure see next page 1

l

r-AAINE YANKEE ATOMIC POWER COMPANY 2

cc with enclosure.

{

Chief Division of Ecological Services 1

Bureau of Sport Fisheries & Wildlife i

U. S. Depart. ent of the Interior

'lasnington, 2. C. 20249 Dr. 'lilliam Canningnam FDA Research Chemist Bureau of Standards % Itchnolooy Desctor 3uilding 235, Roon B-168 Gaithersburg, Md.

20899 I

1 1

)

I l

l MaineYankee 6.t uAutt typsycnv # ou uami tuycty?

EDISON DR%

AUGUSTA MAINE 04330. (PO't) 6?? dN,8 June 11, 1991 MN-91-92 SEN-91-168 UNITED STATES NUCLEAR REGULATORY COMMISSION Attention:

Document Control Desk Washington, DC 20555

References:

(a)

License No. DPR-36 (Docket No. 50-309)

(b)

NUREG-0020, licensed Operating Reactor Status Summary Report

Subject:

Maine Yankee Monthly Statistical Report - May Gentlemen:

Enclosed please find the Monthly Statistical Report for the Maine Yankee Atomic Power Station for May 1991. Please contact me should you have any further questions.

Very cruly yours, Q

Eb S. E. Nichols, Manager Nuclear Engineering & Licensing SLH/sjj Enclosures c:

Mr. Thomas T. Martin Mr. E. H. Trottier Mr. Charles S. Marschall Mr. Patrick J. Dostie SEN91168,ltr s[u, [

m m mm 1

FDR ALocU ty~,000S p R

fnDR

OPERATING DATA REPORY Dockot No.:

53-339 Doto:

11/Jun/91 CoCpletod By:

S.

L.

HALL

(

Telephone 207-622-486u i

1.

Unit Name...................,...................

HAINE YANKEE 2.

Reporting Period................................

Hav 1991

3. Licensed Thermal Power (HWt)....................

2700 4.

Nameplate Rating (Gross HWe)....................

890 5.

Design Electrical Rating (Net HWe)..............

840 6.

Maximum Dependable Capacity (Gross HWe).........

870__

7.

Haximum Dependable Capacity (Net HWe)...........

830 8.

If Changen in Capacity Ratings (Items Number 3-7)

Since Last Report, Give Reasons:

NO CHANGES 9.

Power Level to Which Restricted, if Any (Net HWe)

10. Reasons for Restrictions, if Any:

THIS HONTH YEAR-TO-DATE CUHULATIVE

11. Hours In Reporting Period 714.00 3,673,00

12. Number of Hours Reactor Was Critical...........

40.00 2.555.20 129.784.11

13. Reactor Reserve Shutdown Hours..................

0,00 0.00 0.00

14. Hours Generator On-line..

1.30 2,488.00 126.017.53

15. Unit Reserve Shutdown Hours..................

O, 0 E-0.00 0.00

16. Gross Thermal Energy Generated (HWH)........

475.00

__6.564.501.00 293.741.244.00

17. Gross Electrical Energy Generated (HWH)........

120.00 2.200,_140.00 96.483.510.00

18. Het Electrical Energy Generated (HWH)........

120.00 2.132.756.00 92.422.363.00

19. Unit Service Factor......

0,17 68.67 77.50

20. Unit Availabilty Factor..

0.17 68.67 77.50

21. Unit Capacity Factor (Using HDC Net)........

0.02 70.92 71.28

22. Unit Capacity Factor 0.02 70.08 69.60 (Using DER Net)....

23. Unit Forced Outage Rate..

99.83 31.33_

7.59 12 4. Shutdowns Scheduled Over Next 6 Honths:

HONE

25. If Shutdown at End of Report Period, Estimated Date of Startup:

N/A t

l

4 f

. [j.

Docket No

~ 50-399 Unit Names Maine Yankee 1.'

Date:

96-19-91 Completed By:

S.

L. Hall Telephone:

207-622-4868 Report Honths. Hay, 1991 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCES At the beginning of the month, the unit wau shut down due to a tailure in the Main Transformer (X-1A) on April 25, 1991.

on ' Hay 30, 'the operators were making preparations to phase on liise when-the reactor tripped due to low Steam Generator level.

On May 31, the unit phased on-line and remained on line for the remainder of the month.

L.

i. '

i 1

r-i l'

LAVERAGE DAILY. UNIT PONER LEVEL i

FOR MAY 1991 Docket No.:

50-309 Unit HAINE YANKEB Date:

10/Jun/91 Completed By:

S.

L.

HALL Telephone:

207-622-4868 i

L Doy-Avg. Daily Power Level Day Avg. Daily Power Level (HWe-Net)

(HWe-Net) 1 0

16 0

2 0

17 0

3.

0 18 O

i =

~4-0 19 O'

$=

0-20 O.

' i.

6 0

21 0

(

-7 0

22 0

8 0

23 0

9 0

24 0

10 0

25 O

~11 0

26 0

-12 0

27 0

13 0-28' 0

14 29 0

'O 151 0

30

.0 31 5

h l'

F i

n v---.

..,,->y-y

% e

' UNIT SHUTDONNS AND.PONER REDUCTIONS Docket No.:

50-339 FOR HAY 1991 Unit HAINE YANKEE Date:

10/Jun/91' Completed By:

S.

L.

HALL Telephones 207-622-4868 Page:

1 of 1 Nurber 03-91-12 04-91-12 Dato 910429 I

910530 Type (1)-

[

F F

Duration (Hours) 742.7 0

Reason (2)

A L

A Hothod-(3) l 3

3 LER #

l 91-005-0 L

91-006-0 l

System Coda (4)

EB CH Cocponent Code (5)

TRANS-Z HTEXCH-F On April 29, a On May 30, prior failure of the to phasing on main transformer line, the reactor (X-1A) resulted in tripped on low cause and an automatic trip Steam Generator Corrective from 1001 power.

level.

The unit Action The unit phased phased on line on

-on-line on May 31, May 31.

and remained on line for the rest of the month.

1.

TYPE:

2.

REASON: (cont) 4.

SYSTEM CODE:

(F)orced F-Administrative Exhibit G-Instructions

-(S)cheduled G-Operational Error tor Preparation of Data H-Other (Explain)

Entry Sheets for 2.

REASON Licensee Event Report A-Equipment Failure 3.

METHOD:

(LER) File (NUREG.0161)

B-Haintenance or Test 1-Hanual C-Refueling 2-Manual Scram S.

COMPONENT CODE:

D-Regulatory Restriction 3-Automatic Scram Exhibit I-Same source E-Operator Training &

4-Other (Explain) as above.

License Examination

UNITED STATES O asco

/ '

'o,,

NUCLEAR REGULATORY COMMISSION 2

g WALd6NGTON, D C. 205b5 5

I June 28, 1991 o,

a

%,... * /

50-443 DOCKET NO(S).

EIS Review Coordinator EPA Region 1 JFK Federal Building Boston, Massachusetts 02203

SUBJECT:

PUBLIC SERVICE COMPANY OF NEW HAMPSHIRE - SEABROOK STATION, UNIT 1 The following documents concerning our review of the subject f acility are transmitted for your in ormation.

i DESQFJ10NDF DOCUMENT

_ DATED Notice of Receipt of Application Draf t/ Final Environmental Statement Notice of Availability of Draft / Final Environmental Statement Safety Evaluation Report, or Supplement No.

Environmental Assessment and Finding of No Signihcaat impact Notice of issuance of Environmental Assessment Notice of Consideration of Issuance of Facility Operating License or Amendment to Facility Operating License Biweekly Notice: Applications and Amendments to Operating Licenses invplyj.ntNdgnjf cant Hagris_GgnAtqnt See Pagels) t Exemption Construction Permit No. CPPR-

. Amendment No.

Facility Operating License No.

._ __,Arnendment No.

Order X

Monthly Operating Report for May 1991 transmitted by tetter. ggg)

AnnuallSemi-Annual Report:

transmitted by Letter Other Office of Nuclear Reactor Regulation Enciosures:

As Stated with enclosure cc:

see next page l

Public Service Company of 2

New Hampshire cc with enclosure:

Chief, Division of Ecological Services Bureau of Sport Fisheries & Wildlife U, 5. Department of the Interiof Washington, D. C. 20240 Dr. William Cunningham FDA Research Chemist Bureau of Standards & Technology Reactor Building 235 Room B-108 Gaithersburg, Maryland 20899

{

l 3..

,e New Hampshire Yankee t"r2s""-"

Chief Executive Othcer NYN 91094 June 14,1991 United States Nuclear Regulatory Commission Washington, DC 20555 Attention:

Document Control Desk

Reference:

Facility Operating License NPF-86 Dacket No. 50 443 S ubject:

Monthly Operating Report Gentlemen:

Enclosed please find Monthly Operating Report 91-05.

This report addresses the operating und shutdown experience relating to Seabrook Station Unit I for the month of M ay, 1991 and is submitted in accordance with the requirements of Seabrook Station Technical Specification 6.8.1.5.

Very truly yours, gf y~a/f Ted C. Feigdaum Enclosure (s)

TCF:WJT/t ad cc:

Mr. Thomas T. Martin Regional Administrator United States Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 Mr. Gordon E. Edison, Sr. Project Manager Project Directorate i 1 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Noel Dudley NRC Senior Resident inspector P.O. Box 1149 Seabrook, NH 03874 9terH ?O 12 910531 PDR ADOCK 05000443 7 2 R

PDR I

31 New Hampshire Yankee Division of Public Service Company of New Hampshire

((f j

V - >-

- - a- -

...-..-.. -....~..-=

-.~...

..-...~..

. ~. ~. - -......-.... - - - -

5

=

e.

't e

New if ampshire Yankee June 14,1991 ENCL.OSURE 1 TO NYN.91094 k

t 9

e d

)

i

- -,. - -- -.. ~,... ~... -.. -., _ - _ _ _ _. -

v:

OPERATING DATA REPORT D00KET NO.

50-443 UNIT Seabrook 1 DATE 06/14/91 COMPLETED BY P. Nardone TELEPHONE (603) 474-95?l (Ext. 4074)

OPERATING STATUS 1.

Unit Name:

Seabrook Station Unit 1 j

'2.

Reporting-Period MAY 1991 J

~

-3.

Licensed Theruml Power (HWt):

3411 4.

Nameplate Rating (Gross MWe):

1197-5.

Design' Electrical Rating (Net HWe):

1148 6.

Maximum Dependable _ Capacity (Gross HWe):

1200

-7.

Maximum Dependable Capacity (Net MWe):

1150 8.

If Changes occur in Capacity Ratings (Items Number 3 Through 7)

Since Last Report, Give Reasons:

Not Applicable 9.

Power Level To Which Restricted, If Any:

None

10. Reasons For Restrictions. If Any:

Not Applicable This Month Yr.-to-Date Cumulative

11. Hours In Reporting-Period 744.0 3623.0 40512.0

12. Number Of Hours Reactor Was Critical 744.0 3450,2 9169,5 13, Reactor Reserve Shutdown Hours 0.0 0.0 953.3

14. Hours Generator On-Line 744.0 3421.6 7549.0

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (HWH) 2535734 11033000 23633325

17. Gross Elec. Energy Generated (MWH) 883933 3842776 8114693_'

18. Net Electrical Energy Generated (MWH) 850934 3688169 7782167

19. Unit Service Factor:

100.0 94.4 90.2

20. Unit Availability Factor 100,0 94.4 90.2

21. Unit-Capacity Factor (Using MDC Net) 99.5 88.5 85.6

22. Unit Capacity Factor (Using DER Net) 99.6 88.7 85.8

23. Unit Forced Outage-Rate 0.0 5.6 9.8

24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each):

REFUELING. 07/27/91. 67 DAYS

25. If Shut Down At End Of Report Period, Estimated Date Of Startup: Not Applicable

NOTE: Values based on accumulated hours starting 08/19/90, date Regular Full Power Operation began.

1 of 4

.. ~.

.p--

.y AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-443 UNIT Seabrook 1 DATE 06/14/91 COMPLETED BY P. Nardone TELEPHONE (603) 474-952.1 (Ext. 4074)

MONTH MAY, 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1

'1148 16 1146 2

1148 17 1146 3

1146 18-1144 4

-1146 3J 1144 5

1145 20 1144-6-

1146 21 1144

-7 1147 22

-1144 8

1147 23 1141 9

1146 24 1143 10 1145 25 1144 l-11 1145' 26.

1142 12 1147 27 1142 11 3 -

1146 28-

=1126 14 1147 29 1128 15 1146 30 1141 L

31 1139 L

INSTRUCTIONS-

.On this format,' list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to-the nearest whole megawatt.

2 of 4 l

l

tiNIT Si!UTUUWNS AND POJER REDUCTIONS DOCKET NO.

30 443 g

UNIT Seabrock 1

~

DATE 06/14/91 REPORT MONTH MAY. 1991 COMPLETED BY P. Nardone TELEPHONE (603) 474-9521 (Ext. 4074:

3 No.

Date Type Iruration Reason?

Method of Licensee Cause & Corrective (Hours)

Shutting Event Action to Down Reactor 3 Report i Prevent Eecurrence Fage 1 of 1 NO ENTRIES FOR 'HIS MONTH I

2 3

F: Forced Reason:

Method:

S: Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance er Test 2-Manual Scram C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continued from E-Operater Training & License Examination previous month F-Administrative 5-Power Reduction G-Operr.tional Error (Explain)

(Duration - 0)

H-Other (Explain) 9-Other (Explain) 3 of 4

+ 4.

4 DOCKET NO. __ 10-443 UNIT Seabrook 1 DATE 06/14/91 COMFLETED BY _ft_Nat one d

TELEPHONE (603) 474-95?1 (Ext. 4074)

REFUFLING INFOR!MTU;N kFnUEST

1. Name of facility:

Seabrook Un!t 1

2. Scheduled date for next refueling shutdown:

07/27/91

3. Scheduled date for restart following refueling:

10/02/01

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amer.dment?

Yes, the removal of the Residual Heat Pamoa 1 System Autoclosure Interlock

5. Scheduled date(s) for submitting licensing sction end supporting information:

New Hampshire Yankee Letter NYN-91011, submitted on January 24, 1991

6. Important licensing conriderations associated with refueling, e.g.,

new or different fuel design or suppliet. unteviewed dusign or performance analysis methods, significart changes in fuel design, new operating procedures None

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pools (a)

In Core 193 (b) 0

8. The present licensed.eent fuel pool storage capacity and the size of any increase in licenwed storage capacity that has been requested or is planned, in number of fuel assemblies:

Present licensed capacity:

1236 No increase in storage capacity requested or planned.

9. The projected date of the last refueling that can be discharged tu the spent fuel pool assuming the present licensed capacity:

Licensed capacity of 1236 fuel essemblies based on sixteen annual refuelings and full core offload capability.

The current licensed capacity is =lequate until at least the year 2007.

4 of 4

_ _ - _ _ - -

ML20248J419

Contents

Text

SUBJECT:

Dear Sir:

SUBJECT:

SUMMARY

SUBJECT:

Subject:

Dear Sir:

Dear Sirs:

SUMMARY

= = * * * * * =

SUBJECT:

Enclosures:

References:

Subject:

SUMMARY

SUBJECT:

Reference:

Navigation menu

ML20248J419

Text

SUBJECT:

Dear Sir:

SUBJECT:

SUMMARY

SUBJECT:

Subject:

Dear Sir:

Dear Sirs:

SUMMARY

= = * * * * * =

SUBJECT:

Enclosures:

References:

Subject:

SUMMARY

SUBJECT:

Reference:

Navigation menu

Search