ML20199B114: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 17: Line 17:
=Text=
=Text=
{{#Wiki_filter:,
{{#Wiki_filter:,
CONNECTICUT Y A N K E P.                   AT O MIC POWER COMPANY HADDAM NECK FMNT 362 INJUN HOLLOW ROAD e EAST HAMPTON. CT 06424-3099 November 15,1997 Re: Technical Specification 6.9.1-8 Docket No. 50-213 CY-970-122 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 In accordance with reporting requirements of Technical Specification 6.9.1.8, the Connectbit Yankee liaddam Neck Plant Monthly Operating Report 97-10 covering operations for the period October 1,1997 to October 31,1997 is hereby forwarded.
CONNECTICUT Y A N K E P.
Very truly yours, Russell A. Mellor                               4 Director of Site Operations and Decommissioning Iladdam Neck Station g { n LJ...
AT O MIC POWER COMPANY HADDAM NECK FMNT 362 INJUN HOLLOW ROAD e EAST HAMPTON. CT 06424-3099 November 15,1997 Re: Technical Specification 6.9.1-8 Docket No. 50-213 CY-970-122 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 In accordance with reporting requirements of Technical Specification 6.9.1.8, the Connectbit Yankee liaddam Neck Plant Monthly Operating Report 97-10 covering operations for the period October 1,1997 to October 31,1997 is hereby forwarded.
RAM /bom                                                                                                     k' cc:       (1)     Regional Administrator, Region I h
Very truly yours, Russell A. Mellor 4
U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 I   I (2)     William J. Raymond Sr. Resident Inspector Connecticut Yankee
Director of Site Operations and Decommissioning Iladdam Neck Station g { n LJ...
                  .e 4   .m o
k' RAM /bom cc:
l R
(1)
Regional Administrator, Region I h
U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 I
I (2)
William J. Raymond Sr. Resident Inspector Connecticut Yankee o
.e 4
.m l
R


Connecticut Yankee Atomic Power Company 1laddam Neck Plant Iladdam. Connecticut Monthly Operating Report No. 97-10 For The Month of October 1997
Connecticut Yankee Atomic Power Company 1laddam Neck Plant Iladdam. Connecticut Monthly Operating Report No. 97-10 For The Month of October 1997


Elantfacratine Summary The Haddam Neck Plant has been shut down since July 22,1996 and on December 4, 1996, the Connecticut Yankeu Atomic Power Company (CYAPCO) Board of Directors voted to permanently and immediately cease operations prior to expiration of its license.                             ,
Elantfacratine Summary The Haddam Neck Plant has been shut down since July 22,1996 and on December 4, 1996, the Connecticut Yankeu Atomic Power Company (CYAPCO) Board of Directors voted to permanently and immediately cease operations prior to expiration of its license.
The removal of fuel from the reactor vessel started on November 13, 1996.                                       As of November 15,1996, all fuel assemblies were permanently removed from the reactor and placed in the spent fuel pool for temporary storage.
The removal of fuel from the reactor vessel started on November 13, 1996.
As of November 15,1996, all fuel assemblies were permanently removed from the reactor and placed in the spent fuel pool for temporary storage.
On December 5,1996, pursuant to 10CFR50.82(a)(1)(i) and iOCFR50.6 s. ',1)(ii),
On December 5,1996, pursuant to 10CFR50.82(a)(1)(i) and iOCFR50.6 s. ',1)(ii),
CYAPCO provided docketed wrtification to the NRC that it has decided to permanently cease operations at the Haddam Neck Plant and that fuel has been permanently removed from the reactor.
CYAPCO provided docketed wrtification to the NRC that it has decided to permanently cease operations at the Haddam Neck Plant and that fuel has been permanently removed from the reactor.
CYAPCO submited the Post-Shutdown Decommissioning Activities Report (PSDAR) and the site-specific decommissioning cost estimate in accordance with 10CFR50.82 on August 22,1997.
CYAPCO submited the Post-Shutdown Decommissioning Activities Report (PSDAR) and the site-specific decommissioning cost estimate in accordance with 10CFR50.82 on August 22,1997.
On October 27,1997 the NRC held an infomational meeting at the Haddam Killingworth High Schoolin Higganum, CT to solicit public comments on the PSDAR.
On October 27,1997 the NRC held an infomational meeting at the Haddam Killingworth High Schoolin Higganum, CT to solicit public comments on the PSDAR.
      -__m       ---- - _ _ - - - , , _ ~ - _ - - _ - - _ _ - - - - - - - _ _ _ _ - - -    ------_ - _ _ . - _ - - _ _ _ - .- ________ __
-__m
---- - _ _ - - -,, _ ~ - _ - - _ - - _ _ - - - - - - - _


                                                                                                          ?..   .'[~     , .Z \ _        ,
?...'[~
                  ..                                                                                '
'
* M y n*
* M y n* *
* e + ,.[
,.Z \\ _
4 '._                                 ,                                                                              * ~ _,
,.[
__e                                                                                               *l*'- ...
e +
* F_ *3-         gR u-- u m u,     .,.
* ~ _,
e-   ,-.#ww-                 +
4 '._
                                                          , NRC OPERATING STAWS REPORT Haddam Neck
__e
*l*'-...
* F_ *3-gR
_u-- u m u,
e-
,-.#ww-
+
, NRC OPERATING STAWS REPORT Haddam Neck
: 1. Dockets 50 213-
: 1. Dockets 50 213-
: 2. Repcrting Period 10/97           Outage + On line Hours 745.0 +         0,0 -
: 2. Repcrting Period 10/97 Outage + On line Hours 745.0 +
745.0
0,0 745.0
            - 3. Utility contact s K.w. Ennons (20D 267 3654
- 3. Utility contact s K.w. Ennons (20D 267 3654
: 4. Licensed Thermal Power.(Wt)* 2825
: 4. Licensed Thermal Power.(Wt)* 2825
: 5. Nameplate Arging (Gross Wels 667 x 0.9
: 5. Nameplate Arging (Gross Wels 667 x 0.9
* 600.3
* 600.3
          -6 Des' m diectrical Rating (Not We!s 582
-6 Des' m diectrical Rating (Not We!s 582
            -1. Ma .mm Dependable . Capacity (Gross We) t 586.9
-1.
              . Maximum Dependable Capacity (Not Wel 3 560.1
Ma
.mm Dependable. Capacity (Gross We) t 586.9
*. Maximum Dependable Capacity (Not Wel 3 560.1
: 9. If changes occur above since last report, reasor.s are: M it
: 9. If changes occur above since last report, reasor.s are: M it
: 10. P>wer level to which restricted, if any (Net We): N/A 11, Reasons for restriction, if any: N/A MONTH           U..R TO.DATE                           Ct.HULATIVE
: 10. P>wer level to which restricted, if any (Net We): N/A 11, Reasons for restriction, if any: N/A MONTH U..R TO.DATE Ct.HULATIVE
: 12. Report period hours:                                             745.0                 7,296.0                         261.528.0
: 12. Report period hours:
: 13. Hours reactor critical                                             0. 0 -                       0.0                     199,493.6
745.0 7,296.0 261.528.0
: 14. Reactor reserve shutdown hours:                                     0.0                         0.0                         1. .* 0 5. 0
: 13. Hours reactor critical
: 15. Hours generator on line                                             0.0                         0.0                     193.539.3
: 0. 0 -
: 16. Unit reserve shutdown houest                                     74s.0                     %7,295.0                         8.341.0
0.0 199,493.6
: 17. Gross thermal energy generated (WtH)                                 0.0                         0.0               335.551,124.0 *
: 14. Reactor reserve shutdown hours:
: 18. Cro's electrical energy generated (WeHl                             0.0                         0.0               110,009,804.0 *
0.0 0.0
: 19. Net electrical energy generated (WeHl:                       -1,314.4               -13,832.3                     104,500,691.3
: 1..* 0 5. 0
* 20 Unit servtce f actori                                                 0.0                         0.0                             74.0
: 15. Hours generator on line 0.0 0.0 193.539.3
: 21. Unit availabtllty factor                                           99.9                     100.0                               77 3
: 16. Unit reserve shutdown houest 74s.0
: 22. (nit capacity f actor uslag MDC net                                 0.0                         0.0                               12.1
%7,295.0 8.341.0
        .23. Unit capacity factor using DER nets-                                 0.0                         0.0                               68.7
: 17. Gross thermal energy generated (WtH) 0.0 0.0 335.551,124.0 *
: 24. Unit forced outage rate:                                             0.0                       0.0                               -6.3 2 5.: Forc'd-outage hoursi                                               0.0                       0.0                       12,970.0 3J. Shutdowns scheduled over next 6 months (tyoe,date, duration; NONb
: 18. Cro's electrical energy generated (WeHl 0.0 0.0 110,009,804.0 *
: 19. Net electrical energy generated (WeHl:
-1,314.4
-13,832.3 104,500,691.3
* 20 Unit servtce f actori 0.0 0.0 74.0
: 21. Unit availabtllty factor 99.9 100.0 77 3
: 22. (nit capacity f actor uslag MDC net 0.0 0.0 12.1
.23. Unit capacity factor using DER nets-0.0 0.0 68.7
: 24. Unit forced outage rate:
0.0 0.0
-6.3 2 5.: Forc'd-outage hoursi 0.0 0.0 12,970.0 3J. Shutdowns scheduled over next 6 months (tyoe,date, duration; NONb
: 27. If current 1 shutdown, estimated startup dates N/A l
: 27. If current 1 shutdown, estimated startup dates N/A l
1
-1 l
                                                                                                                                                                -1 l
I
I l
- e cumulative values f rom the first criticallyyy/24 /67). (The remaining cumulat3ve values are from the first date of
      - e cumulative values f rom the first criticallyyy/24 /67) . (The remaining cumulat3ve values are from the first date of
-icommercialoperat' ton,01/olfs,3,
          -icommercialoperat' ton,01/olfs,3,
.J a.
: a. - . ~ .
- u
                                                          .J
-. ~.
                                                          -u
- 7.,.-, y
  *                                                                                                                                            - 7 ., .-, y
.e d ;.. s -
                          .e d ;. . s -
.+ e
+
1 -
1 -
                                          .+ e    +        .      .                                      s     .+,       . . .        ~ . - . . w-. .,
s
.+,
~. -..
w-.


e CLWJTWE REPORT 10/97 CtMJ'JTIVE
e CLWJTWE REPORT 10/97 CtMJ'JTIVE
: 1. Report rettoi hourst                                                               265,392.0
: 1. Report rettoi hourst 265,392.0
: 2. h re generator on line,                                                             195,0s3.9
: 2. h re generator on line, 195,0s3.9
: 3. Hours reactor etaticali                                                           201,702.3
: 3. Hours reactor etaticali 201,702.3 4.
: 4. On line net elect rical energy generated (MWeH):                             104,74b,s54.2
On line net elect rical energy generated (MWeH):
: 5. Of f-line st ation service electrical energy utilised (MWeH) e                     26*,735.5
104,74b,s54.2
: 6. Transf orwier losses (MWelt) ,                                                     276,153.1
: 5. Of f-line st ation service electrical energy utilised (MWeH) e 26*,735.5
: 7. Effective full power dayss                                                           7,734.1
: 6. Transf orwier losses (MWelt),
: 9. Ef f ective f ull p<rver hours ,                                                   185,617.3
276,153.1
: 9. Cot'e 14srn-u[: (MWtC"PrNii                                                       218.701.8 10 " umber of spector shetdownss                                                               307 Note; all values at. cumulative f rom the first criticality !C104 hrs. 07/24/67).
: 7. Effective full power dayss 7,734.1
: 9. Ef f ective f ull p<rver hours,
185,617.3
: 9. Cot'e 14srn-u[: (MWtC"PrNii 218.701.8 10 " umber of spector shetdownss 307 Note; all values at. cumulative f rom the first criticality !C104 hrs. 07/24/67).


AVERAGE DAILY POWER LEVEL
AVERAGE DAILY POWER LEVEL
          .                                                                                                                      :4 Docket No:                         50-213 Unit: Haddam Neck Date:         11/12/97 Completed by:                     K.W. Emmons Month: Oct-97                                               Telephone: (860)447-1791 X6572 AVERAGE POWER LEVEL                                                         AVERAGE POWER LEVEL DM                         (MWe-Net)                   DM                                     (MWe-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                     <
:4 Docket No:
7                           0                         23                                         0 8                           0                         24                                         0 9                           0                         25                                         0 1C                           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 l
50-213 Unit: Haddam Neck Date:
11/12/97 Completed by:
K.W. Emmons Month: Oct-97 Telephone: (860)447-1791 X6572 AVERAGE POWER LEVEL AVERAGE POWER LEVEL DM (MWe-Net)
DM (MWe-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
1C 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
l


4 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-213 UNIT NAME                                       lindram Neck DATE                                     11/01/97 COMPLETED BY                                       K.W. Emmons         ,
4 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
TELEPHONE 1860) 447-1791 X6572                                               l' REPORT MONTH October 1932 No.         Date     Typn1     Duration       Reason 2   Method of             License                                         System Component -           Cause & Corrective (Hours)                   Shutting             Event                                           Code 4 Codc5                 Actiran to Down Reactor 3       Report #
50-213 UNIT NAME lindram Neck DATE 11/01/97 COMPLETED BY K.W. Emmons TELEPHONE 1860) 447-1791 X6572 l
Prevent Recurrence 96-05 07/22/96           S         745             F           4                 N/A                                               N/A 1F: Forced             2 Reason                                           3 Method 41EEE Standard 805 1984, S: Scheduled           A - Equipment Failure (Explain)                       1 - Manual
REPORT MONTH October 1932 No.
                          " Recommended Practices B - Maintenance or Test                             2 - Manual Scram                                               -
Date Typn1 Duration Reason 2 Method of License System Component -
for System Identificaticn in C - Refueling                                       3 - Automatic Scram Nuclear Power Pl ants and D - Regulatory Restriction                           4 - Continued from Previous Month         Related Facilities" E Operator Training & License Examination           5 - Power Reduction (Duration = 0)
Cause & Corrective (Hours)
F - A'ministrative                                   6 - Other (Explain)
Shutting Event Code 4 Codc5 Actiran to Down Reactor 3 Report #
Prevent Recurrence 96-05 07/22/96 S
745 F
4 N/A N/A 1F: Forced 2 Reason 3 Method 41EEE Standard 805 1984, S: Scheduled A - Equipment Failure (Explain) 1 - Manual
" Recommended Practices B - Maintenance or Test 2 - Manual Scram for System Identificaticn in C - Refueling 3 - Automatic Scram Nuclear Power Pl ants and D - Regulatory Restriction 4 - Continued from Previous Month Related Facilities" E Operator Training & License Examination 5 - Power Reduction (Duration = 0)
F - A'ministrative 6 - Other (Explain)
SIEEE Standard 805A-1983, G - Operational Error (Explain)
SIEEE Standard 805A-1983, G - Operational Error (Explain)
                            " Recommended Practices
" Recommended Practices


1
1 s
* s 9
9 I
I
H + Other (Explain) for Unique identification in-Power Plants and Related -
    ,                              H + Other (Explain) for Unique identification in-Power Plants and Related -
Facilities - Component Function Identifiers"
Facilities - Component Function Identifiers"


I
I REFUELING INFORMATION REQUEST October 1997 1.
                            ,                                                    REFUELING INFORMATION REQUEST October 1997                                                               #
Name of the facility:
: 1. Name of the facility:                         Haddam Neck _
Haddam Neck _
: 2. Scheduled date for next refueling outage: n/a (decommissioningl
2.
: 3. Scheduled date for restart following refueling: n/a (decommissionin;g
Scheduled date for next refueling outage: n/a (decommissioningl 3.
: 4.   (a)         Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Scheduled date for restart following refueling: n/a (decommissionin;g 4.
DL3 (b)       If answer is yes, what, in general, will these be?
(a)
nLa (c)       If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine if any unreviewed safety questions are associated with the core reload?
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
n/a (d)     If no such review has taken place, when it it scheduled?
DL3 (b)
nla
If answer is yes, what, in general, will these be?
: 5. Scheduled date(s) for submitting licensing action and supporting information:
nLa (c)
nLa
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine if any unreviewed safety questions are associated with the core reload?
: 6. Important licensing considerations associated with refueling, e.g., new or different fuel dasign or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
n/a (d)
DLa
If no such review has taken place, when it it scheduled?
: 7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
nla 5.
In Core: (a) Q                                                                     In Spent Fuel Pool: (b) J 019
Scheduled date(s) for submitting licensing action and supporting information:
: 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemb!ies:
nLa 6.
Etesant storage caoacitv: 1480
Important licensing considerations associated with refueling, e.g., new or different fuel dasign or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
: 9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming present license capacity:
DLa 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
In Core: (a) Q In Spent Fuel Pool: (b) J 019 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemb!ies:
Etesant storage caoacitv: 1480 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming present license capacity:
DLa
DLa
_ _ _ _ - _ _ - - _ - -                _ __          ._    _ _ _ _ . _ _ _ - _            _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _                  _    _-}}
_-}}

Latest revision as of 08:43, 10 December 2024

Monthly Operating Rept for Oct 1997 for Haddam Neck Plant
ML20199B114
Person / Time
Site: Haddam Neck, 05000231  File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 10/31/1997
From: Emmons K, Mellor R
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CY-970-122, NUDOCS 9711180216
Download: ML20199B114 (9)


Text

,

CONNECTICUT Y A N K E P.

AT O MIC POWER COMPANY HADDAM NECK FMNT 362 INJUN HOLLOW ROAD e EAST HAMPTON. CT 06424-3099 November 15,1997 Re: Technical Specification 6.9.1-8 Docket No. 50-213 CY-970-122 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 In accordance with reporting requirements of Technical Specification 6.9.1.8, the Connectbit Yankee liaddam Neck Plant Monthly Operating Report 97-10 covering operations for the period October 1,1997 to October 31,1997 is hereby forwarded.

Very truly yours, Russell A. Mellor 4

Director of Site Operations and Decommissioning Iladdam Neck Station g { n LJ...

k' RAM /bom cc:

(1)

Regional Administrator, Region I h

U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 I

I (2)

William J. Raymond Sr. Resident Inspector Connecticut Yankee o

.e 4

.m l

R

Connecticut Yankee Atomic Power Company 1laddam Neck Plant Iladdam. Connecticut Monthly Operating Report No. 97-10 For The Month of October 1997

Elantfacratine Summary The Haddam Neck Plant has been shut down since July 22,1996 and on December 4, 1996, the Connecticut Yankeu Atomic Power Company (CYAPCO) Board of Directors voted to permanently and immediately cease operations prior to expiration of its license.

The removal of fuel from the reactor vessel started on November 13, 1996.

As of November 15,1996, all fuel assemblies were permanently removed from the reactor and placed in the spent fuel pool for temporary storage.

On December 5,1996, pursuant to 10CFR50.82(a)(1)(i) and iOCFR50.6 s. ',1)(ii),

CYAPCO provided docketed wrtification to the NRC that it has decided to permanently cease operations at the Haddam Neck Plant and that fuel has been permanently removed from the reactor.

CYAPCO submited the Post-Shutdown Decommissioning Activities Report (PSDAR) and the site-specific decommissioning cost estimate in accordance with 10CFR50.82 on August 22,1997.

On October 27,1997 the NRC held an infomational meeting at the Haddam Killingworth High Schoolin Higganum, CT to solicit public comments on the PSDAR.

-__m


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

?...'[~

'

  • M y n* *

,.Z \\ _

,.[

e +

  • ~ _,

4 '._

__e

  • l*'-...
  • F_ *3-gR

_u-- u m u,

e-

,-.#ww-

+

, NRC OPERATING STAWS REPORT Haddam Neck

1. Dockets 50 213-
2. Repcrting Period 10/97 Outage + On line Hours 745.0 +

0,0 745.0

- 3. Utility contact s K.w. Ennons (20D 267 3654

4. Licensed Thermal Power.(Wt)* 2825
5. Nameplate Arging (Gross Wels 667 x 0.9
  • 600.3

-6 Des' m diectrical Rating (Not We!s 582

-1.

Ma

.mm Dependable. Capacity (Gross We) t 586.9

  • . Maximum Dependable Capacity (Not Wel 3 560.1
9. If changes occur above since last report, reasor.s are: M it
10. P>wer level to which restricted, if any (Net We): N/A 11, Reasons for restriction, if any: N/A MONTH U..R TO.DATE Ct.HULATIVE
12. Report period hours:

745.0 7,296.0 261.528.0

13. Hours reactor critical
0. 0 -

0.0 199,493.6

14. Reactor reserve shutdown hours:

0.0 0.0

1..* 0 5. 0
15. Hours generator on line 0.0 0.0 193.539.3
16. Unit reserve shutdown houest 74s.0

%7,295.0 8.341.0

17. Gross thermal energy generated (WtH) 0.0 0.0 335.551,124.0 *
18. Cro's electrical energy generated (WeHl 0.0 0.0 110,009,804.0 *
19. Net electrical energy generated (WeHl:

-1,314.4

-13,832.3 104,500,691.3

  • 20 Unit servtce f actori 0.0 0.0 74.0
21. Unit availabtllty factor 99.9 100.0 77 3
22. (nit capacity f actor uslag MDC net 0.0 0.0 12.1

.23. Unit capacity factor using DER nets-0.0 0.0 68.7

24. Unit forced outage rate:

0.0 0.0

-6.3 2 5.: Forc'd-outage hoursi 0.0 0.0 12,970.0 3J. Shutdowns scheduled over next 6 months (tyoe,date, duration; NONb

27. If current 1 shutdown, estimated startup dates N/A l

-1 l

I

- e cumulative values f rom the first criticallyyy/24 /67). (The remaining cumulat3ve values are from the first date of

-icommercialoperat' ton,01/olfs,3,

.J a.

- u

-. ~.

- 7.,.-, y

.e d ;.. s -

.+ e

+

1 -

s

.+,

~. -..

w-.

e CLWJTWE REPORT 10/97 CtMJ'JTIVE

1. Report rettoi hourst 265,392.0
2. h re generator on line, 195,0s3.9
3. Hours reactor etaticali 201,702.3 4.

On line net elect rical energy generated (MWeH):

104,74b,s54.2

5. Of f-line st ation service electrical energy utilised (MWeH) e 26*,735.5
6. Transf orwier losses (MWelt),

276,153.1

7. Effective full power dayss 7,734.1
9. Ef f ective f ull p<rver hours,

185,617.3

9. Cot'e 14srn-u[: (MWtC"PrNii 218.701.8 10 " umber of spector shetdownss 307 Note; all values at. cumulative f rom the first criticality !C104 hrs. 07/24/67).

AVERAGE DAILY POWER LEVEL

4 Docket No:

50-213 Unit: Haddam Neck Date:

11/12/97 Completed by:

K.W. Emmons Month: Oct-97 Telephone: (860)447-1791 X6572 AVERAGE POWER LEVEL AVERAGE POWER LEVEL DM (MWe-Net)

DM (MWe-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

1C 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

l

4 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-213 UNIT NAME lindram Neck DATE 11/01/97 COMPLETED BY K.W. Emmons TELEPHONE 1860) 447-1791 X6572 l

REPORT MONTH October 1932 No.

Date Typn1 Duration Reason 2 Method of License System Component -

Cause & Corrective (Hours)

Shutting Event Code 4 Codc5 Actiran to Down Reactor 3 Report #

Prevent Recurrence 96-05 07/22/96 S

745 F

4 N/A N/A 1F: Forced 2 Reason 3 Method 41EEE Standard 805 1984, S: Scheduled A - Equipment Failure (Explain) 1 - Manual

" Recommended Practices B - Maintenance or Test 2 - Manual Scram for System Identificaticn in C - Refueling 3 - Automatic Scram Nuclear Power Pl ants and D - Regulatory Restriction 4 - Continued from Previous Month Related Facilities" E Operator Training & License Examination 5 - Power Reduction (Duration = 0)

F - A'ministrative 6 - Other (Explain)

SIEEE Standard 805A-1983, G - Operational Error (Explain)

" Recommended Practices

1 s

9 I

H + Other (Explain) for Unique identification in-Power Plants and Related -

Facilities - Component Function Identifiers"

I REFUELING INFORMATION REQUEST October 1997 1.

Name of the facility:

Haddam Neck _

2.

Scheduled date for next refueling outage: n/a (decommissioningl 3.

Scheduled date for restart following refueling: n/a (decommissionin;g 4.

(a)

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

DL3 (b)

If answer is yes, what, in general, will these be?

nLa (c)

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine if any unreviewed safety questions are associated with the core reload?

n/a (d)

If no such review has taken place, when it it scheduled?

nla 5.

Scheduled date(s) for submitting licensing action and supporting information:

nLa 6.

Important licensing considerations associated with refueling, e.g., new or different fuel dasign or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

DLa 7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:

In Core: (a) Q In Spent Fuel Pool: (b) J 019 8.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemb!ies:

Etesant storage caoacitv: 1480 9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming present license capacity:

DLa

_-