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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT MONTHLY OPERATING REPORT No. 85-12 FOR THE MONTH OF DECEMBER.1985 8604010314 e60115 PDR ADDCK 05000213 R             PDR                                   l
CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT MONTHLY OPERATING REPORT No. 85-12 FOR THE MONTH OF DECEMBER.1985 8604010314 e60115 PDR ADDCK 05000213 R
                                                              }
PDR
}


PLANT OPERATIONS The plant operated in a coastdown mode for the month of December, 1985. There were no load reductions during the month.
PLANT OPERATIONS The plant operated in a coastdown mode for the month of December, 1985. There were no load reductions during the month.
                                                                  /
/


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SYSTEM     MAINTEN/SCt       DECEMBER 1985 EFFECT ON CORRECTIVE ACTION SPECIAL PRECAUTIONS OR             M Al.FilNCT I OFI           SAFE   TAKEN TO PI(EVENT TAKEN'l'O PROVIDE COMPONENT     CAUSE               RESULT     OPERATION   REPETITION     Folt REAGYOR SAFI7IT 1)URI NG REP.il R There were no reportable items for the raonth of December
SYSTEM MAINTEN/SCt DECEMBER 1985 EFFECT ON CORRECTIVE ACTION SPECIAL PRECAUTIONS OR M Al.FilNCT I OFI SAFE TAKEN TO PI(EVENT TAKEN'l'O PROVIDE COMPONENT CAUSE RESULT OPERATION REPETITION Folt REAGYOR SAFI7IT 1)URI NG REP.il R There were no reportable items for the raonth of December


. e         ,
e AVERAGE DAILY UNIT POWER LEVEL DOCKET No.
AVERAGE DAILY UNIT POWER LEVEL DOCKET No. 50-213 Conn. Yankee UNIT Haddam Neck DATE Jan. 15, 1986 COMPLETED 3Y C. B. Dean TELEPHONE (203) 267-2556 MONTH:   December 1985 DAY     AVERAGE DAILY POWER LEVEL               DAY   AVERAGE DAILY POWER LEVEL (MWe-Net)                                   (MWe-Net) 1               538                           17           518 2               539                           18           516 3               542                           19           518 4               544                           20           518 5               542                           21           516 6               535                           22           513 7               532~                                         511 23 8               529                           24           509 9               527                           25           506 10             532                           26           504 11             535                           27           502 12             529                           28 500 13             524                           29           498           .
50-213 Conn. Yankee UNIT Haddam Neck DATE Jan. 15, 1986 COMPLETED 3Y C. B. Dean TELEPHONE (203) 267-2556 MONTH:
14             522                           30           496 15             520                           31           494 16             521 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Complete the nearest whole megawatt.
December 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 538 17 518 2
539 18 516 3
542 19 518 4
544 20 518 516 5
542 21 513 6
535 22 511 7
532~
23 8
529 24 509 506 9
527 25 504 10 532 26 502 11 535 27 500 12 529 28 13 524 29 498 14 522 30 496 15 520 31 494 16 521 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.
Complete the nearest whole megawatt.
(9/77) l
(9/77) l


i
i a
_                                                                                                                                                                    a l
l CONNECTICUT YANKEE
CONNECTICUT YANKEE
-REACTOR-COOLANT-DATA---
                                                          -REACTOR-COOLANT-DATA---
MONTH: DECEMBER 1985 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM
MONTH: DECEMBER 1985 REACTOR COOLANT ANALYSIS                                                                                                   MINIMUM                                       AVERAGE         MAXIMUM
.. rrrrrrrrrrrrrrrrreTvr.w rrrrr.r rrr.. v..... v. rr r rrr.. rrverrr.-rrrr r., +
    . . rrrrrrrrrrrrrrrrreTvr.w rrrrr.r rrr. . v. . . . . v. rr r rrr. . rrverrr.-rrrr r., +
PH 9 25 DEGREES C 5.78E+00 :
PH 9 25 DEGREES C                                                                                             :            5.78E+00 :                                     6.81E+00       8.01E+00 :
6.81E+00 8.01E+00 :
CONDUCTIVITY (UMHOS/CM)                                                                                       :            3.50E-01 :                                     8.65E-01 :     1.70E+00
CONDUCTIVITY (UMHOS/CM) 3.50E-01 :
-CMtORIDES-t PPM P                                                                                               :-<5 7 00E-02-:-<5 r 00E--02-:-<5v 00E     DISSOLVED OXYGEN (PPB)                                                                                       : <5 . 00E+00 : <5 . 00E+00 : <5.00Ef00 :
8.65E-01 :
BORON (PPM)                                                       '
1.70E+00
1.50E-01 : 2.20E+00 : 4.50E+01 :
-CMtORIDES-t PPM P
-LI-THIUM-( PPM )                                                                               -- :-1. 00E-02 -:-2.12E-02-8-4 r10E-02-;
:-<5 7 00E-02-:-<5 r 00E--02-:-<5v 00E DISSOLVED OXYGEN (PPB)
  -TOTAL GAMMA ACT. (UC/ML)                                                                                     :            4.25E-01 ! 6.78E-01 :                                         1.04E+00 :
: <5 00E+00 : <5 00E+00 : <5.00Ef00 :
IDDINE-131 ACT. (UC/ML)                                                                                     :            4.55E-03 : 6.45E-03 :                                         1.50E-02 :
BORON (PPM) 1.50E-01 :
-I-131-/-I-133-R AT-I D                                                                                             -1.15E+00-:--14-37E+00 -
2.20E+00 :
4.50E+01 :
-LI-THIUM-( PPM )
-- :-1. 00E-02 -:-2.12E-02-8-4 r10E-02-;
-TOTAL GAMMA ACT. (UC/ML) 4.25E-01 !
6.78E-01 :
1.04E+00 :
IDDINE-131 ACT. (UC/ML) 4.55E-03 :
6.45E-03 :
1.50E-02 :
-I-131-/-I-133-R AT-I D
-1.15E+00-:--14-37E+00 -
* 1484E+00
* 1484E+00
* CRUD (MG/ LITER)                                                                                             : <1.00E-02 : <1.00E-02 : <1.00E-02 :
* CRUD (MG/ LITER)
: TRITIUM (UC/ML)                                                                                             :            3.17E-01 : 3.99E-01 1 5.16E-01 HYDROGEN-(CC/KG)                                                                                               -3.48E+01_:                                               3.73E+01 - :   3.99E+01_:
: <1.00E-02 : <1.00E-02 : <1.00E-02 :
AERATED LIGUID WASTE PROCESSED (GALLONS):                                                                                                               1.66E+05
: TRITIUM (UC/ML) 3.17E-01 :
-WASTE-LIQUID-PROCESSED-THROUGH-BORON - RECOVERY ( GALLONS )-:-1-,8CE+05 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE):                                                                                                                           2.18E+00 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):                                                                                                                             0.00E+00 W-                           e dew- -A--%e-44w w%emwk.a-ng,+.-mm*w.e 4                                               gw,w*,hw-p
3.99E-01 1 5.16E-01 HYDROGEN-(CC/KG)
'$ O                                                                                                                       - -
-3.48E+01_:
wm ae--ry eswha wm                               h.             ++'-e       L 44-emw-                           aw                           w, M'                                                                                                           MMnm-em- r gg-mas mi we e s d4e.-ew9=*Eue                   Ws.m-         samps,_a.- wew..-A       m. e,pw mnwgem     mm,
3.73E+01 - :
3.99E+01_:
AERATED LIGUID WASTE PROCESSED (GALLONS):
1.66E+05
-WASTE-LIQUID-PROCESSED-THROUGH-BORON - RECOVERY ( GALLONS )-:-1-,8CE+05 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE):
2.18E+00 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):
0.00E+00 W-e dew- -A--%e-44w w%emwk.a-ng,+.-mm*w.e 4 gw,w*,hw-p
'$ O ae--ry eswha wm h.
++'-e L 44-emw-aw wm w,
M' MMnm-em-r gg-mas mi we e d4e.-ew9=*Eue Ws.m-samps,_a.-
wew..-A
: m. e,pw mnwgem mm, s


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  . s           .
NRC Operating Status Report Haddam Neck
NRC Operating Status Report Haddam Neck
: 1. Decket: 50-213
: 1. Decket: 50-213
: 2. Reporting Period: 12/85       Outage + On-line Hours:       0.0 + 744.0 = 744.0
: 2. Reporting Period: 12/85 Outage + On-line Hours:
0.0 + 744.0 = 744.0
: 3. Utility
: 3. Utility


Line 93: Line 168:
J.P. Drago (203) 267-2556 ext 452
J.P. Drago (203) 267-2556 ext 452
: 4. Licensed Thereal Power (MWt): 1825
: 4. Licensed Thereal Power (MWt): 1825
: 5. Naseplate Rating (Gross MWe): 667 x 0.9 = 6C0.3                                                                     '
: 5. Naseplate Rating (Gross MWe): 667 x 0.9 = 6C0.3
: 6. Design Electrical Rating (Nat Me): 582
: 6. Design Electrical Rating (Nat Me): 582
: 7. Maximus Eependable Capacity (Gross Me): 595.8
: 7. Maximus Eependable Capacity (Gross Me): 595.8
Line 99: Line 174:
: 9. If changes occur above since last report, reasons are: NDNE
: 9. If changes occur above since last report, reasons are: NDNE
: 10. Poner level to which restricted, if any (Net Me): N/A
: 10. Poner level to which restricted, if any (Net Me): N/A
: 11. Reasons for restriction, if any: N/A MCNTH         YEAR-TO-DATE         CUMULATIVE
: 11. Reasons for restriction, if any: N/A MCNTH YEAR-TO-DATE CUMULATIVE
: 12. Report period hour;:                                         744.0             8,760.0           157,800.0
: 12. Report period hour;:
: 13. Hours reactor critical:                                     744.0             8,682.4           136,399.4
744.0 8,760.0 157,800.0
: 14. Reattor reserve shutdcan hours:                                 0.0               21.0             1,285.0
: 13. Hours reactor critical:
: 15. Hours generator on-line:                                     744.0             8,597.3           130,801.8
744.0 8,682.4 136,399.4
: 16. Unit reserve shutdown hours:                                   0.0               24.3               398.0
: 14. Reattor reserve shutdcan hours:
: 17. Gross thereal energy generated (MWtH):               1,244,703.0           14,928,729.0       227,115,912.0 t
0.0 21.0 1,285.0
: 18. Gross electrical energy generated (MeH):               407,549.0           4,371,719.0       74,530,867.0 1
: 15. Hours generator on-line:
: 19. Net electrical energy generated (MeH):                 387,151.9           4,638,105.2       70,899,170.3 8
744.0 8,597.3 130,801.8
: 20. Unit service factor:                                         100.0                 98.1               82.9
: 16. Unit reserve shutdown hours:
: 21. Unit availability f actor:                                   100.0                 98.4               8h.1
0.0 24.3 398.0
: 22. Unit capacity factor using MDC net:                           91.5                 93.1               82.5
: 17. Gross thereal energy generated (MWtH):
: 23. Unit capacity facter using DER net:                           89.4                 91.0               77.3
1,244,703.0 14,928,729.0 227,115,912.0 t
: 24. Unit forced cutap rate:                                         0.0                 1.9                 5.7
: 18. Gross electrical energy generated (MeH):
: 25. Forced outage hours:                                           0.0               162.7             7,868.8
407,549.0 4,371,719.0 74,530,867.0 1
: 19. Net electrical energy generated (MeH):
387,151.9 4,638,105.2 70,899,170.3 8
: 20. Unit service factor:
100.0 98.1 82.9
: 21. Unit availability f actor:
100.0 98.4 8h.1
: 22. Unit capacity factor using MDC net:
91.5 93.1 82.5
: 23. Unit capacity facter using DER net:
89.4 91.0 77.3
: 24. Unit forced cutap rate:
0.0 1.9 5.7
: 25. Forced outage hours:
0.0 162.7 7,868.8
: 26. Shutdowns scheduled o<er next 6 sonths (type,date, dt. ration): REFUELING, 1/4/86, 11 WEE 4 DURATION.
: 26. Shutdowns scheduled o<er next 6 sonths (type,date, dt. ration): REFUELING, 1/4/86, 11 WEE 4 DURATION.
: 27. If currently shutdown, estimated startup date: N/A
: 27. If currently shutdown, estimated startup date: N/A
                                                                                                                              \
\\
f Cuaulative values from the first criticality (07/24/67). (The rc?ainir} tumulative values are from the first date of cessercial operation, 01/01/68).
f Cuaulative values from the first criticality (07/24/67). (The rc?ainir} tumulative values are from the first date of cessercial operation, 01/01/68).


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b 6
REFUELING INFORMATION REQUEST
REFUELING INFORMATION REQUEST 1.
: 1. Name of facility
Name of facility
                                                                        ,i Connecticut Yankee Atedic Power Company J
,i Connecticut Yankee Atedic Power Company J
: 2. Scheduled date for next refueling shutdown.
2.
January 4, 19863                                                         -
Scheduled date for next refueling shutdown.
t
January 4, 19863 t
: 3. Scheduled date for restart following refueling.
3.
March 20, 1986
Scheduled date for restart following refueling.
: 4.     (a) Will. refueling or resumption of operation thereafter require a technical speci-fication' change or other license amendment?
March 20, 1986 4.
(a) Will. refueling or resumption of operation thereafter require a technical speci-fication' change or other license amendment?
YES (b) If answer is yes, what, in general, will these be?
YES (b) If answer is yes, what, in general, will these be?
l.. Revise the allowance factors in calculating core power peaking.
l.. Revise the allowance factors in calculating core power peaking.
: 2. Revise the axial offset limits for 4 loop and 3 loop ogeration.
: 2. Revise the axial offset limits for 4 loop and 3 loop ogeration.
: 3. Revise the RCS mass flow specification due to anticipathd S/G work.
: 3. Revise the RCS mass flow specification due to anticipathd S/G work.
l                       (c) If answer is no, has the reload fuel design and core configuration been reviewed       )
l (c) If answer is no, has the reload fuel design and core configuration been reviewed
by your Plant Safety Review Committee to determine whether any unreviewed safety     l questions are associated with the core reload (Ref. 10 CFR Section 50.59)?           l I
)
l                             Core reload design in progress.
by your Plant Safety Review Committee to determine whether any unreviewed safety l
l l                       (d). If no such review has taken place, when is it scheduled?
questions are associated with the core reload (Ref. 10 CFR Section 50.59)?
January 1986
l I
: 5. Scheduled date(s) for. submitting proposed licensing action and supporting information.
l Core reload design in progress.
December 1985
l l
: 6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
(d). If no such review has taken place, when is it scheduled?
NO
January 1986 5.
: 7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
Scheduled date(s) for. submitting proposed licensing action and supporting information.
(a)   157 (b) 545
December 1985 6.
: 8. The present licensed spent fuel pool storage captcity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.
Important licensing considerations associated with refueling, e.g.,
1168
new or different fuel design 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 the pre'sent licensed capacity.
NO 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
(a) 157 (b) 545 8.
The present licensed spent fuel pool storage captcity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.
1168 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the pre'sent licensed capacity.
1994 to 1995
1994 to 1995
                                              - - - _ _ _ - _ _ _ _ _ _              _}}
_}}

Latest revision as of 22:43, 10 December 2024

Monthly Operating Rept for Dec 1985
ML20154S543
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 12/31/1985
From: Dean C
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20154S538 List:
References
NUDOCS 8604010314
Download: ML20154S543 (9)


Text

--

CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT MONTHLY OPERATING REPORT No. 85-12 FOR THE MONTH OF DECEMBER.1985 8604010314 e60115 PDR ADDCK 05000213 R

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PLANT OPERATIONS The plant operated in a coastdown mode for the month of December, 1985. There were no load reductions during the month.

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SYSTEM MAINTEN/SCt DECEMBER 1985 EFFECT ON CORRECTIVE ACTION SPECIAL PRECAUTIONS OR M Al.FilNCT I OFI SAFE TAKEN TO PI(EVENT TAKEN'l'O PROVIDE COMPONENT CAUSE RESULT OPERATION REPETITION Folt REAGYOR SAFI7IT 1)URI NG REP.il R There were no reportable items for the raonth of December

e AVERAGE DAILY UNIT POWER LEVEL DOCKET No.

50-213 Conn. Yankee UNIT Haddam Neck DATE Jan. 15, 1986 COMPLETED 3Y C. B. Dean TELEPHONE (203) 267-2556 MONTH:

December 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 538 17 518 2

539 18 516 3

542 19 518 4

544 20 518 516 5

542 21 513 6

535 22 511 7

532~

23 8

529 24 509 506 9

527 25 504 10 532 26 502 11 535 27 500 12 529 28 13 524 29 498 14 522 30 496 15 520 31 494 16 521 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.

Complete the nearest whole megawatt.

(9/77) l

i a

l CONNECTICUT YANKEE

-REACTOR-COOLANT-DATA---

MONTH: DECEMBER 1985 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM

.. rrrrrrrrrrrrrrrrreTvr.w rrrrr.r rrr.. v..... v. rr r rrr.. rrverrr.-rrrr r., +

PH 9 25 DEGREES C 5.78E+00 :

6.81E+00 8.01E+00 :

CONDUCTIVITY (UMHOS/CM) 3.50E-01 :

8.65E-01 :

1.70E+00

-CMtORIDES-t PPM P

-<5 7 00E-02-:-<5 r 00E--02-:-<5v 00E DISSOLVED OXYGEN (PPB)
<5 00E+00 : <5 00E+00 : <5.00Ef00 :

BORON (PPM) 1.50E-01 :

2.20E+00 :

4.50E+01 :

-LI-THIUM-( PPM )

-- :-1. 00E-02 -:-2.12E-02-8-4 r10E-02-;

-TOTAL GAMMA ACT. (UC/ML) 4.25E-01 !

6.78E-01 :

1.04E+00 :

IDDINE-131 ACT. (UC/ML) 4.55E-03 :

6.45E-03 :

1.50E-02 :

-I-131-/-I-133-R AT-I D

-1.15E+00-:--14-37E+00 -

  • 1484E+00
  • CRUD (MG/ LITER)
<1.00E-02 : <1.00E-02 : <1.00E-02 :
TRITIUM (UC/ML) 3.17E-01 :

3.99E-01 1 5.16E-01 HYDROGEN-(CC/KG)

-3.48E+01_:

3.73E+01 - :

3.99E+01_:

AERATED LIGUID WASTE PROCESSED (GALLONS):

1.66E+05

-WASTE-LIQUID-PROCESSED-THROUGH-BORON - RECOVERY ( GALLONS )-:-1-,8CE+05 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE):

2.18E+00 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):

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NRC Operating Status Report Haddam Neck

1. Decket: 50-213
2. Reporting Period: 12/85 Outage + On-line Hours:

0.0 + 744.0 = 744.0

3. Utility

Contact:

J.P. Drago (203) 267-2556 ext 452

4. Licensed Thereal Power (MWt): 1825
5. Naseplate Rating (Gross MWe): 667 x 0.9 = 6C0.3
6. Design Electrical Rating (Nat Me): 582
7. Maximus Eependable Capacity (Gross Me): 595.8
8. Maxieus Dependable Capacity (Net M e): 569
9. If changes occur above since last report, reasons are: NDNE
10. Poner level to which restricted, if any (Net Me): N/A
11. Reasons for restriction, if any: N/A MCNTH YEAR-TO-DATE CUMULATIVE
12. Report period hour;:

744.0 8,760.0 157,800.0

13. Hours reactor critical:

744.0 8,682.4 136,399.4

14. Reattor reserve shutdcan hours:

0.0 21.0 1,285.0

15. Hours generator on-line:

744.0 8,597.3 130,801.8

16. Unit reserve shutdown hours:

0.0 24.3 398.0

17. Gross thereal energy generated (MWtH):

1,244,703.0 14,928,729.0 227,115,912.0 t

18. Gross electrical energy generated (MeH):

407,549.0 4,371,719.0 74,530,867.0 1

19. Net electrical energy generated (MeH):

387,151.9 4,638,105.2 70,899,170.3 8

20. Unit service factor:

100.0 98.1 82.9

21. Unit availability f actor:

100.0 98.4 8h.1

22. Unit capacity factor using MDC net:

91.5 93.1 82.5

23. Unit capacity facter using DER net:

89.4 91.0 77.3

24. Unit forced cutap rate:

0.0 1.9 5.7

25. Forced outage hours:

0.0 162.7 7,868.8

26. Shutdowns scheduled o<er next 6 sonths (type,date, dt. ration): REFUELING, 1/4/86, 11 WEE 4 DURATION.
27. If currently shutdown, estimated startup date: N/A

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f Cuaulative values from the first criticality (07/24/67). (The rc?ainir} tumulative values are from the first date of cessercial operation, 01/01/68).

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REFUELING INFORMATION REQUEST 1.

Name of facility

,i Connecticut Yankee Atedic Power Company J

2.

Scheduled date for next refueling shutdown.

January 4, 19863 t

3.

Scheduled date for restart following refueling.

March 20, 1986 4.

(a) Will. refueling or resumption of operation thereafter require a technical speci-fication' change or other license amendment?

YES (b) If answer is yes, what, in general, will these be?

l.. Revise the allowance factors in calculating core power peaking.

2. Revise the axial offset limits for 4 loop and 3 loop ogeration.
3. Revise the RCS mass flow specification due to anticipathd S/G work.

l (c) If answer is no, has the reload fuel design and core configuration been reviewed

)

by your Plant Safety Review Committee to determine whether any unreviewed safety l

questions are associated with the core reload (Ref. 10 CFR Section 50.59)?

l I

l Core reload design in progress.

l l

(d). If no such review has taken place, when is it scheduled?

January 1986 5.

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

December 1985 6.

Important licensing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

NO 7.

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

(a) 157 (b) 545 8.

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

1168 9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the pre'sent licensed capacity.

1994 to 1995

_