ML19344B534: Difference between revisions
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{{#Wiki_filter:- - - - - | {{#Wiki_filter:- - - - - | ||
(. | (. | ||
G | G | ||
* OPERATING DATA REPORT l | |||
DOCKET NO. 80-321 DATE 10-10-80 COSIPLETED BY Pz t undarwood TELEPHONE 112-J6/-/781 OPERATING STATUS | |||
OPERATING DATA REPORT l | |||
DOCKET NO. 80-321 | |||
' latch 1 Notes I 1. Unit Name: | ' latch 1 Notes I 1. Unit Name: | ||
: 2. Reporting Period: 9-80 i | : 2. Reporting Period: 9-80 i | ||
: 3. Licensed Thermal Power (Mb ti: 74'26 4' | : 3. Licensed Thermal Power (Mb ti: 74'26 4' | ||
Line 37: | Line 30: | ||
: 7. Staximum Dependable Capacity (Net alwe): 764.3 | : 7. Staximum Dependable Capacity (Net alwe): 764.3 | ||
: 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Give Reasons: | : 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Give Reasons: | ||
: 9. Power Lesel To which Restricted. If Any (Net SIWE): | : 9. Power Lesel To which Restricted. If Any (Net SIWE): | ||
: 10. Reasons For Restrictions.If Any: | : 10. Reasons For Restrictions.If Any: | ||
Line 43: | Line 35: | ||
This Manth Yr..to.Date Cumulatise | This Manth Yr..to.Date Cumulatise | ||
. II. Hours in Reporting Pesiod 720 6575 41639 ' | . II. Hours in Reporting Pesiod 720 6575 41639 ' | ||
: 12. Number Of Hours Reactor Was Critical 703.5 _' 5593.3 31391.3 | : 12. Number Of Hours Reactor Was Critical 703.5 _' 5593.3 31391.3 | ||
: 13. Reactor Resesse Shutdown Hours 0.0 O.0 0.0 4 | : 13. Reactor Resesse Shutdown Hours 0.0 O.0 0.0 4 | ||
: 14. Hours Generator On Line 693.0 5153.I 29421.5 | : 14. Hours Generator On Line 693.0 5153.I 29421.5 | ||
Line 53: | Line 43: | ||
3784830 20055770 ' | 3784830 20055770 ' | ||
: 18. Net Electrical Energy Generated (5tWH) 487132 3606894 10068827 | : 18. Net Electrical Energy Generated (5tWH) 487132 3606894 10068827 | ||
: 19. Unit Sersice Factor 96.2 78.4 70.7 | : 19. Unit Sersice Factor 96.2 78.4 70.7 | ||
: 20. Unit Availability Factor 96.? 78.4 70.7 ) | : 20. Unit Availability Factor 96.? 78.4 70.7 ) | ||
Line 66: | Line 55: | ||
! = | ! = | ||
INITIA L CRITICALITY INITIA L ELECTRICITY l-i Coil \tERCIA L OPER ATION i | INITIA L CRITICALITY INITIA L ELECTRICITY l-i Coil \tERCIA L OPER ATION i | ||
l :i i | l :i i | ||
..L ~~- | ..L ~~- | ||
t y I. | t y I. | ||
1 i | 1 i | ||
a- --x.-..-..-..- | a- --x.-..-..-..- | ||
8010210 | 8010210 | ||
_ _ ~ _ _ | _ _ ~ _ _ | ||
4 2... f _ - | 4 2... f _ - | ||
? | ? | ||
AVERAGE DAILY UNIT POWER LEVEL | AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-321 (JNIT Hatch 1 DATE 10-10-80 4 C0\1PLETED BY P. R. Underwood | ||
DOCKET NO. 50-321 (JNIT Hatch 1 DATE 10-10-80 4 C0\1PLETED BY P. R. Underwood | |||
_ TELEPilONE 912-367-7781 C: MONTil 9-80 - | _ TELEPilONE 912-367-7781 C: MONTil 9-80 - | ||
DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL * | DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL * | ||
(MWe-Net) (MWe. Net i 3 746 751 17 2 744 is 753 3 741 748 19 4 447 20 743 5 429 21 391 6 574 376 22 7 635 23 691 | (MWe-Net) (MWe. Net i 3 746 751 17 2 744 is 753 3 741 748 19 4 447 20 743 5 429 21 391 6 574 376 22 7 635 23 691 8 622' 24 702 9 743 742 25 to - | ||
8 622' 24 702 | |||
9 743 742 25 to - | |||
753 26 741 11 749 27 731 | 753 26 741 11 749 27 731 | ||
"' 743 12 23 747 13 582 747 29 14 685 30 745 15 749 _ | "' 743 12 23 747 13 582 747 29 14 685 30 745 15 749 _ | ||
31 16 751 INSTRUCTIONS On this format. list the nerage daily unit power lese! in MWe Net for each day in the reportmg 14.inth. Compute the nearest whole megawatt. | 31 16 751 INSTRUCTIONS On this format. list the nerage daily unit power lese! in MWe Net for each day in the reportmg 14.inth. Compute the nearest whole megawatt. | ||
(0177) | (0177) | ||
* c.I : | * c.I : | ||
3- ____n.,,, - - .-. | 3- ____n.,,, - - .-. | ||
._ . - - ~~ - - - | ._ . - - ~~ - - - | ||
. ~ '. | . ~ '. | ||
DOCKETNo. 50-321 UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT N AME Hatch 1 . | DOCKETNo. 50-321 UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT N AME Hatch 1 . | ||
DATE IU-lU-W t. | |||
DATE IU-lU-W | |||
t. | |||
COMPLETED BY P R. Underwood REPORT MONTH 9-M TELEPHONE 917-367-77H1 _ , | COMPLETED BY P R. Underwood REPORT MONTH 9-M TELEPHONE 917-367-77H1 _ , | ||
~. | ~. | ||
- E e | - E e | ||
Line 126: | Line 86: | ||
9u Action to p,,,,,,g,,,,,,,c, | 9u Action to p,,,,,,g,,,,,,,c, | ||
* $$ 2 j #5 c Repori # | * $$ 2 j #5 c Repori # | ||
a 3 NA Hil HTEXCil Rx scram due to false high MSR level , | |||
a | 80-46 800904 F 11.2 A caused by LS being grounded. 4 NA HH HTEXCH Unit on startup ramp from above shut-80-47 800904 'F 53.2 A 5 down, #80-46 12.9 D 5 NA RB CONROD ibduced load to perform rod pattern 80-48 800907 F adjustment NA RB CONROD Reduced load to perform turbine test t 80-49 800912 S 21.6 0 5 and rod pattern adjustment l 1 | ||
3 NA Hil HTEXCil Rx scram due to false high MSR level , | |||
80-46 800904 F 11.2 A caused by LS being grounded. 4 NA HH HTEXCH Unit on startup ramp from above shut-80-47 800904 'F 53.2 A 5 down, #80-46 | |||
12.9 D 5 NA RB CONROD ibduced load to perform rod pattern 80-48 800907 F adjustment NA RB CONROD Reduced load to perform turbine test t 80-49 800912 S 21.6 0 5 and rod pattern adjustment l 1 | |||
3 NA ZZ ZZZZZZ Rx scram due to transferring of RPS 80-50 800921 F 15.8 l | 3 NA ZZ ZZZZZZ Rx scram due to transferring of RPS 80-50 800921 F 15.8 l | ||
bus "B" from alt. to normal and a. | bus "B" from alt. to normal and a. | ||
spurious trip on RPS " A" l | spurious trip on RPS " A" l g | ||
3 4 i, I 2 Exhibit G-Instructions Reason: Method: | |||
, F: Forced for Preparation of Data A liguipment Failure (Explain) 1-Manual S: Scheduled Entry Sheets for Licensee n Maintenance of Test 2 Manual Scram. . | , F: Forced for Preparation of Data A liguipment Failure (Explain) 1-Manual S: Scheduled Entry Sheets for Licensee n Maintenance of Test 2 Manual Scram. . | ||
3-Automatic Scram. Event Report ILER) File INUREG- } | 3-Automatic Scram. Event Report ILER) File INUREG- } | ||
Line 147: | Line 99: | ||
(9/77) liether(Emplain) | (9/77) liether(Emplain) | ||
. . j 1 | . . j 1 | ||
i ! | i ! | ||
w y | w y | ||
DOCKET NO. 50-371 UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME Hatch 1 . | DOCKET NO. 50-371 UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME Hatch 1 . | ||
DATE 10-10-R) | DATE 10-10-R) | ||
COMPLETED BY P. R. (Indervood REPORT MONTH 9-80 T1ELEPliONE 912-367-7781 | COMPLETED BY P. R. (Indervood REPORT MONTH 9-80 T1ELEPliONE 912-367-7781 "t.c c Cause & Corrective l Eg Nie. Date h | ||
Cause & Corrective l Eg Nie. Date | |||
h | |||
.!"E 38 | .!"E 38 | ||
}= }. | }= }. | ||
m , se Licensee Event g,7 E3 | m , se Licensee Event g,7 E3 A''3"" '" | ||
A''3"" '" | |||
Prevent Recurrence i | Prevent Recurrence i | ||
mE' g H | mE' g H | ||
$5 a'l j4c R* Port # | $5 a'l j4c R* Port # | ||
5 ftA ZZ ZZZZZZ Unit on startup ramp from above shut-80-51 800921 F 14.0 down, #80-50 , | 5 ftA ZZ ZZZZZZ Unit on startup ramp from above shut-80-51 800921 F 14.0 down, #80-50 , | ||
RB C0flROD ibduced load to perform a rod pattern 80-52 800923 F 4.0 D 5 f1A adjustment ftA WA FILTER Reduced load due to debris stopping ! | RB C0flROD ibduced load to perform a rod pattern 80-52 800923 F 4.0 D 5 f1A adjustment ftA WA FILTER Reduced load due to debris stopping ! | ||
80-53 800927 F 1.0 B 5 ' | 80-53 800927 F 1.0 B 5 ' | ||
up PSW strainers | up PSW strainers | ||
[ | [ | ||
1 l j ' | 1 l j ' | ||
i i | i i | ||
3 4 I 2 Exhibit G-Instructions 1 Method: | 3 4 I 2 Exhibit G-Instructions 1 Method: | ||
F: Forced Reason 1-Manual for Pseparation of Data S: Scheduled A-L iui ment Failure (Explain) Entry Sheets for Licensee B4taintenance of Test 2-Manual Scram. | F: Forced Reason 1-Manual for Pseparation of Data S: Scheduled A-L iui ment Failure (Explain) Entry Sheets for Licensee B4taintenance of Test 2-Manual Scram. | ||
3 Automatic Scram. Event Repost (LER) Fde INUREG-C Refueling . | 3 Automatic Scram. Event Repost (LER) Fde INUREG-C Refueling . | ||
0161) | 0161) | ||
D Regulatory Restriction 4 -Continuations E-Operator Training & Ucense Examination 5-Ioad Reduction 5 t | D Regulatory Restriction 4 -Continuations E-Operator Training & Ucense Examination 5-Ioad Reduction 5 t F Administrative 9-Other (Explain) Exhibit I Same Source GOperational Error (Emplain) | ||
F Administrative 9-Other (Explain) Exhibit I Same Source | |||
GOperational Error (Emplain) | |||
* l (9/77) 11Osher(Explain) | * l (9/77) 11Osher(Explain) | ||
) | ) | ||
a 1 3 | a 1 3 | ||
~ | ~ | ||
NARRATIVE REPORT UNIT 1 Sept. 4th Rx scram at 14:39 due to false high MSR level; scram ' caused by equipment failure of the LS on the MSR; LS was grounded Sept. 4th Startup from above shutdown, #80-46; Rx critical at 20:55, and generator on line at 01:49 on Sept. 5th.; unit -returned to 80% conditions at l | NARRATIVE REPORT UNIT 1 Sept. 4th Rx scram at 14:39 due to false high MSR level; scram ' caused by equipment failure of the LS on the MSR; LS was grounded Sept. 4th Startup from above shutdown, #80-46; Rx critical at 20:55, and generator on line at 01:49 on Sept. 5th.; unit -returned to 80% conditions at l | ||
07:00 on Sept. 7th c | 07:00 on Sept. 7th c | ||
_q-Sept. 7th Reduced load in order to perform final rod pattern adjustment from above startup; unit returned to 80% conditions at 12:00 on Sept. 8th | _q-Sept. 7th Reduced load in order to perform final rod pattern adjustment from above startup; unit returned to 80% conditions at 12:00 on Sept. 8th Sept. 12th Redu*ed load in order to perform weekly turbine tests and rod pattern adjustment; unit returned to 80% conditions at 21:30 on Sept. 13th i | ||
Sept. 21st Rx auto scram at 12:53 due to the transferring of RPS channel "B" bus from alt to normal and a l spurtous trip on RPS channel "A" | |||
. Sept. 21st Startup from above shutdown, #80-50; Rx critical at 23:05,- and generator on line at 04:44 on Sept. 22nd; unit returned to 80% conditions at t ; | |||
Sept. 12th Redu*ed load in order to perform weekly turbine tests and rod pattern adjustment; unit returned to 80% conditions at 21:30 on Sept. 13th | |||
. Sept. 21st Startup from above shutdown, #80-50; Rx critical at 23:05,- and generator on line at 04:44 on | |||
Sept. 22nd; unit returned to 80% conditions at t ; | |||
3 18:45, Sept. 22nd , | 3 18:45, Sept. 22nd , | ||
Sept. 23rd Reduced load in order to perform a rod pattern adjustment; unit returned to 80% conditions at 02:45 on Sapt. 24th Sept. 27th Reduced load due to debris 4 | Sept. 23rd Reduced load in order to perform a rod pattern adjustment; unit returned to 80% conditions at 02:45 on Sapt. 24th Sept. 27th Reduced load due to debris 4 | ||
stopping up PSW strainers | stopping up PSW strainers | ||
; There was no single ' release of radioactivity or single | ; There was no single ' release of radioactivity or single radiation exposure which accounts for more than 10% of the allowable annual-values during September of 1980. | ||
radiation exposure which accounts for more than 10% of the allowable annual-values during September of 1980. | |||
t | t | ||
-1 e | -1 e | ||
4 | 4 | ||
-%g $ $4lh us & %WMMP*M S M MOW > | -%g $ $4lh us & %WMMP*M S M MOW > | ||
8lBP_ | 8lBP_ | ||
* W' ' | * W' ' | ||
* HATCH 1 SAFETY - RELATED MAINTENANCE REQUESTS TO BE-REPORTED FOR' SEPTEMBER 1980 NUMBER DATE COMPLETED DESCRIPTION 50-4447 6-26-80 Calibrated pressure switch on HCU 80-4188 8-28-80 Replaced CRD HCU pressure switch isolation valves; valves were suspected of leaking 80-4187 8-28-80 Replaced CRD HCU pressure switch g isolation valves; valves were suspected of leaking l 80-4186 8-28-80 Replaced CRD HCU pressure switch j isolation valves; valves were i suspected of leaking 80-4178 8-28-80 Replaced CRD HCU pressure switch isolation valves; valves were suspected of teaking j 80-4312 8-19-80 3/4" "B" core spray discharge test connection was found to have cracked between the nipple and j-the 3/4" valve. Replaced old pipe with new piece of pipe 80-4495 8-29-80 Snubber was found- to havc a seal l 1eak; replaced leaking snubber' with new snubber 80-4507 8-29-80 Snubber was found to have a seal | |||
'g leak; removed snubber and rebuilt with all new parts; replaced snubber after being rebuilt 80-04429 8-28-80 Snubber was found- to be leaking fluid; replaced leaking snubber with new snubber l 80-4430 8-28-80 Snubber was .found to be leaking | |||
! fluid; replaced leaking snubber j with new snubber l 80-4486 9-1-80 Replaced- fire detector and-j calibrated I | |||
80-3988 8-29-80 Relocation of #2 fire pump controller D | |||
HATCH 1 SAFETY - RELATED MAINTENANCE REQUESTS TO BE-REPORTED FOR' SEPTEMBER 1980 | |||
NUMBER DATE COMPLETED DESCRIPTION 50-4447 6-26-80 Calibrated pressure switch on HCU 80-4188 8-28-80 Replaced CRD HCU pressure switch isolation valves; valves were suspected of leaking | |||
80-4187 8-28-80 Replaced CRD HCU pressure switch | |||
g isolation valves; valves were suspected of leaking l 80-4186 8-28-80 Replaced CRD HCU pressure switch j isolation valves; | |||
valves were i suspected of leaking 80-4178 8-28-80 Replaced CRD HCU pressure switch isolation valves; valves were suspected of teaking j 80-4312 8-19-80 3/4" "B" core spray discharge test connection was found to have cracked between the nipple and j-the 3/4" valve. Replaced old pipe with new piece of pipe 80-4495 8-29-80 Snubber was found- to havc a seal l 1eak; replaced leaking snubber' | |||
with new snubber 80-4507 8-29-80 Snubber was found to have a seal | |||
'g leak; removed snubber and rebuilt | |||
with all new parts; replaced snubber after being rebuilt | |||
80-04429 8-28-80 Snubber was found- to be leaking | |||
fluid; replaced leaking snubber with new snubber l 80-4430 8-28-80 Snubber was .found to be leaking | |||
! fluid; replaced leaking snubber j with new snubber l 80-4486 9-1-80 Replaced- fire detector and-j | |||
calibrated I | |||
80-3988 8-29-80 Relocation of #2 fire pump controller | |||
D | |||
.T k- | .T k- | ||
- N+f 5 %* &f #4%d OO %% O WM = - bE i W D - | - N+f 5 %* &f #4%d OO %% O WM = - bE i W D - | ||
'}} | '}} |
Latest revision as of 06:16, 18 February 2020
ML19344B534 | |
Person / Time | |
---|---|
Site: | Hatch |
Issue date: | 10/10/1980 |
From: | Underwood P GEORGIA POWER CO. |
To: | |
Shared Package | |
ML19344B529 | List: |
References | |
NUDOCS 8010210421 | |
Download: ML19344B534 (6) | |
Text
- - - - -
(.
G
- OPERATING DATA REPORT l
DOCKET NO.80-321 DATE 10-10-80 COSIPLETED BY Pz t undarwood TELEPHONE 112-J6/-/781 OPERATING STATUS
' latch 1 Notes I 1. Unit Name:
- 2. Reporting Period: 9-80 i
- 3. Licensed Thermal Power (Mb ti: 74'26 4'
- 4. Nameplate Rating (Gross SIWE): 809.3 .
- 5. Design Electrical Rating (Net 5tWe): 777.3
- 6. Maximum Dependable Capacity (Gross SIWE): 796.3
- 7. Staximum Dependable Capacity (Net alwe): 764.3
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Give Reasons:
- 9. Power Lesel To which Restricted. If Any (Net SIWE):
- 10. Reasons For Restrictions.If Any:
i 4
This Manth Yr..to.Date Cumulatise
. II. Hours in Reporting Pesiod 720 6575 41639 '
- 12. Number Of Hours Reactor Was Critical 703.5 _' 5593.3 31391.3
- 13. Reactor Resesse Shutdown Hours 0.0 O.0 0.0 4
- 14. Hours Generator On Line 693.0 5153.I 29421.5
- 15. Unit Reserve Shutdown Hours nn 0.0 0.0 j u 16. Gross Thermal Energy Generated _(MWH) 1575954 13588807 61941842-
~ *
- 17. Gross Electrical Energy Gener'sted (SIWH1 509060 _ , _ ,
3784830 20055770 '
- 18. Net Electrical Energy Generated (5tWH) 487132 3606894 10068827
- 19. Unit Sersice Factor 96.2 78.4 70.7
- 20. Unit Availability Factor 96.? 78.4 70.7 )
- 21. Unit Capacity Factor IUsing SIDC Nett 88.5 71.8 s;o . g
- 22. Unit Capacity ' Factor IUsing DER Net) 87.0 70.6 58.9 4
- 23. Unit Forced Outage Rate 3.8 21. 6 _, 20.9
- 24. Shutdowns Scheduled Oser Next 6 Stonths (Type, Date.and Duration of Eacht: .
Refuelino and torus work, 3-1-81. 13 wks.
l'
- 25. If Shut Down At Er.J Of P.eport Period. Estimated Date of Startup:
- 26. Units in Test Status tPrior to Commercial Operationi: Forecast Achiesed I
! =
INITIA L CRITICALITY INITIA L ELECTRICITY l-i Coil \tERCIA L OPER ATION i
l :i i
..L ~~-
t y I.
1 i
a- --x.-..-..-..-
8010210
_ _ ~ _ _
4 2... f _ -
?
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-321 (JNIT Hatch 1 DATE 10-10-80 4 C0\1PLETED BY P. R. Underwood
_ TELEPilONE 912-367-7781 C: MONTil 9-80 -
DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL *
(MWe-Net) (MWe. Net i 3 746 751 17 2 744 is 753 3 741 748 19 4 447 20 743 5 429 21 391 6 574 376 22 7 635 23 691 8 622' 24 702 9 743 742 25 to -
753 26 741 11 749 27 731
"' 743 12 23 747 13 582 747 29 14 685 30 745 15 749 _
31 16 751 INSTRUCTIONS On this format. list the nerage daily unit power lese! in MWe Net for each day in the reportmg 14.inth. Compute the nearest whole megawatt.
(0177)
- c.I :
3- ____n.,,, - - .-.
._ . - - ~~ - - -
. ~ '.
DOCKETNo. 50-321 UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT N AME Hatch 1 .
DATE IU-lU-W t.
COMPLETED BY P R. Underwood REPORT MONTH 9-M TELEPHONE 917-367-77H1 _ ,
~.
- E e
- ,$g "g' *Y3 Licensee E*, *g " . Cause & Corrective No. Daie $ Ti = g 3g& Event u A u?
9u Action to p,,,,,,g,,,,,,,c,
- $$ 2 j #5 c Repori #
a 3 NA Hil HTEXCil Rx scram due to false high MSR level ,
80-46 800904 F 11.2 A caused by LS being grounded. 4 NA HH HTEXCH Unit on startup ramp from above shut-80-47 800904 'F 53.2 A 5 down, #80-46 12.9 D 5 NA RB CONROD ibduced load to perform rod pattern 80-48 800907 F adjustment NA RB CONROD Reduced load to perform turbine test t 80-49 800912 S 21.6 0 5 and rod pattern adjustment l 1
3 NA ZZ ZZZZZZ Rx scram due to transferring of RPS 80-50 800921 F 15.8 l
bus "B" from alt. to normal and a.
spurious trip on RPS " A" l g
3 4 i, I 2 Exhibit G-Instructions Reason: Method:
, F: Forced for Preparation of Data A liguipment Failure (Explain) 1-Manual S: Scheduled Entry Sheets for Licensee n Maintenance of Test 2 Manual Scram. .
3-Automatic Scram. Event Report ILER) File INUREG- }
C Refueling .
D-Regulatory Restriction 4 -Continuations 0161) 1 E-Operator Training & Ucense Examination 5-Ioad Ibduction i 5
' F-AdministrasIve 9-Other (Explain) Exhibit I- Same Source G-Operational Errot (Emplain) *
(9/77) liether(Emplain)
. . j 1
i !
w y
DOCKET NO. 50-371 UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME Hatch 1 .
DATE 10-10-R)
COMPLETED BY P. R. (Indervood REPORT MONTH 9-80 T1ELEPliONE 912-367-7781 "t.c c Cause & Corrective l Eg Nie. Date h
.!"E 38
}= }.
m , se Licensee Event g,7 E3 A3"" '"
Prevent Recurrence i
mE' g H
$5 a'l j4c R* Port #
5 ftA ZZ ZZZZZZ Unit on startup ramp from above shut-80-51 800921 F 14.0 down, #80-50 ,
RB C0flROD ibduced load to perform a rod pattern 80-52 800923 F 4.0 D 5 f1A adjustment ftA WA FILTER Reduced load due to debris stopping !
80-53 800927 F 1.0 B 5 '
up PSW strainers
[
1 l j '
i i
3 4 I 2 Exhibit G-Instructions 1 Method:
F: Forced Reason 1-Manual for Pseparation of Data S: Scheduled A-L iui ment Failure (Explain) Entry Sheets for Licensee B4taintenance of Test 2-Manual Scram.
3 Automatic Scram. Event Repost (LER) Fde INUREG-C Refueling .
0161)
D Regulatory Restriction 4 -Continuations E-Operator Training & Ucense Examination 5-Ioad Reduction 5 t F Administrative 9-Other (Explain) Exhibit I Same Source GOperational Error (Emplain)
- l (9/77) 11Osher(Explain)
)
a 1 3
~
NARRATIVE REPORT UNIT 1 Sept. 4th Rx scram at 14:39 due to false high MSR level; scram ' caused by equipment failure of the LS on the MSR; LS was grounded Sept. 4th Startup from above shutdown, #80-46; Rx critical at 20:55, and generator on line at 01:49 on Sept. 5th.; unit -returned to 80% conditions at l
07:00 on Sept. 7th c
_q-Sept. 7th Reduced load in order to perform final rod pattern adjustment from above startup; unit returned to 80% conditions at 12:00 on Sept. 8th Sept. 12th Redu*ed load in order to perform weekly turbine tests and rod pattern adjustment; unit returned to 80% conditions at 21:30 on Sept. 13th i
Sept. 21st Rx auto scram at 12:53 due to the transferring of RPS channel "B" bus from alt to normal and a l spurtous trip on RPS channel "A"
. Sept. 21st Startup from above shutdown, #80-50; Rx critical at 23:05,- and generator on line at 04:44 on Sept. 22nd; unit returned to 80% conditions at t ;
3 18:45, Sept. 22nd ,
Sept. 23rd Reduced load in order to perform a rod pattern adjustment; unit returned to 80% conditions at 02:45 on Sapt. 24th Sept. 27th Reduced load due to debris 4
stopping up PSW strainers
- There was no single ' release of radioactivity or single radiation exposure which accounts for more than 10% of the allowable annual-values during September of 1980.
t
-1 e
4
-%g $ $4lh us & %WMMP*M S M MOW >
8lBP_
- W' '
- HATCH 1 SAFETY - RELATED MAINTENANCE REQUESTS TO BE-REPORTED FOR' SEPTEMBER 1980 NUMBER DATE COMPLETED DESCRIPTION 50-4447 6-26-80 Calibrated pressure switch on HCU 80-4188 8-28-80 Replaced CRD HCU pressure switch isolation valves; valves were suspected of leaking 80-4187 8-28-80 Replaced CRD HCU pressure switch g isolation valves; valves were suspected of leaking l 80-4186 8-28-80 Replaced CRD HCU pressure switch j isolation valves; valves were i suspected of leaking 80-4178 8-28-80 Replaced CRD HCU pressure switch isolation valves; valves were suspected of teaking j 80-4312 8-19-80 3/4" "B" core spray discharge test connection was found to have cracked between the nipple and j-the 3/4" valve. Replaced old pipe with new piece of pipe 80-4495 8-29-80 Snubber was found- to havc a seal l 1eak; replaced leaking snubber' with new snubber 80-4507 8-29-80 Snubber was found to have a seal
'g leak; removed snubber and rebuilt with all new parts; replaced snubber after being rebuilt 80-04429 8-28-80 Snubber was found- to be leaking fluid; replaced leaking snubber with new snubber l 80-4430 8-28-80 Snubber was .found to be leaking
! fluid; replaced leaking snubber j with new snubber l 80-4486 9-1-80 Replaced- fire detector and-j calibrated I
80-3988 8-29-80 Relocation of #2 fire pump controller D
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