ML20023D109

Monthly Operating Rept for Apr 1983

ML20023D109
Person / Time
Site:	Three Mile Island
Issue date:	05/13/1983
From:	Smyth C GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20023D107	List: ML20023D106 ML20023D109
References
NUDOCS 8305190247
Download: ML20023D109 (10)

Text

L OPERATING DATA REPORT DOCKET NO.

SC-2S9 DATE Mav 13. 1983 COMPLETED BY C. W. Smyth TELEPHONE / 7' n o^R Rssi OPERATING STATUS Three Mile Island Nuclear Station, Uni: I

1. Unit Name:

2. Reporting Period.

Anril. 1983 2535

3. Licensed Thermal Power (MWt):

871

4. Nameplate Rating (Gross MWe):

019'

. 5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe): {0

//6

7. Maximum Dependable Capacity (Net MWe):

S. If Changes Occur in Capacity Ratings (Items Number 3 Tnrough 7) Since Last Report. Give Reasons:

9. Power Level To Which Restricted,1f Any (Net MWe):

10. Reasons For Restrictions,if Any:

This Month Yr..to.Date Cumulaiise 719.

2879.

75912.

II. Hours in Reporting Period 0.0 0.0 31731.S

12. Number Of Hours Rea,etor was Critical 0.0 0.0 839.5

13. Reactor Reserve Shutdown Hours 0.0 0.0 31153,9

14. Hours Generator On.Line OU 0.0 0.0

15. Unit Reserve ShutdowTi Hours 0.0 0.0 76531071.

16. Gross Therma! Energy Generated (MWH)

U*

U-D-o*33v.

17. Gross Electrical Energy Generated (MWH) u.

o.

.a c, uva.:.

l

15. Net Electrical Energy Generated (MWH) 0.0 0.0 41.1

19. Unit Service Factor O.O u.v 41,1

20. Unit Availability Factor 0.0 0.0 40.1

21. Unit Capacity Factor (Using MDC Neti 0.0 0.0 38.3

22. Unit Capacity Factor (Using DER Neti 100.0 100.0 34.5

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Next 6 Months (Type.Date.and Duration of Each1:

25. If Shut Down At End Of Report Period. Estimated Date of Startup:

26. Units in Test Status (Prior to Commercial Operationi:

Forecast Achined INITI AL CRITICALITY INITIAL ELECTRICITY l

COMMERCIAL OPERATION I

B305190247 830513

(":, _ _ $

PDR ADOCK 05000289 R

PDR

AVER AGE D AILY UNIT POWER LEVEL-DOCKET NO. _5_0-2E9

-I UNIT DATE COMPLETED BY C. W. Smyth (717) 948-8551 TELEPHONE Pril, 1983 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DA!LY POWER LEVEL (MWe Net) g y w,.y,,,

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OPERATIONS

SUMMARY

The unit was shutdown the entire month by order of the NRC.

Core cooling was provided by the Decay Heat Removal system.

MAJOR SAFETY REIATED MAINTENANCE During the month-restart modifications continued and the following major maintenance items were performed.

The Once Through Steam Generator (OTSG) Repair Program continued in the month of April with the completion of tube plugging, felt plug free path-ing and drip testing of the "A" Generator.

"B" Generator work activities consisted of felt-plug free pathing, eddy current testing and a second drip test.

Work activities on both Generators will continue into the month of Nby.

Th's Pressurizer Valve Inspection Program continued with the inspection pro-1

~

grem,com' 1eted and the reassembly of valves RC-RV-2 and RC-V-2.

The in-p spection work included UT of studs and x-ray /PT work on valve parts. These

\\ inspections were performed with satisfactory results. The reinstallation 4

Nof valve 'RC-V-1 was completed with the welding in of the leak off piping.

s 3he Pressurizer (RC-T-2) inspection was completed during the month with an internal. camera inspection, manned entry for visual inspection and swipe xsamples, hydrolasing and a follow up camera inspection. Remote ultrasonic testing was performed on various internal welds. Magnetic particle and visual

_g Inspections were performed on the manway studs. All inspections were performed j

'g\\ i h wt satisfactory results.

The manway cover was reinstalled completing this Owork.

'\\

q.

l

\\\\g Waste Gas Disposal System work continued during the month with the completion y,A ?q of diaphragm changeout of system valves.

Repairs to relief valve WDG-V-12 are'in progress. A satisfactory pneumatic leak test was performed on WDG-V-4 s

'and WDG-V-158.

s s; -

(

\\

s Ihe, Snubler Testing Program was ' completed during the month with the following i

a

_ [T snuthe3s tremdved, repaired, tested satisfactory and reinstalled. MS-209 failed

[.

to lock up.

See report LER 83-012.

l

.c FR-111 EF-85 VR-26

'\\

BS-26A FW-110 BS-23 l

yi MS-209-('

MUE-43 BS-24 k

MS-211 MS-206 PR-37 s

MS-219

'FW-112 SPSE-2 I

T BS-27 MS-222 BS-22 s

Air Handling Syste= purge valve seat replacement work was completed durine the l'

month of April with new seats installed in valves AH-V-1A and AH-V-lC.

Local j

Leak Rate Testing of these valves were performed satisfactorily.

1 Decay Heat Removal pump DH-P-1A repairs were completed during the month with

..)

(. - reassembly of1 pump internals, cotor/ pump coupling alignment and satisfactory hit; testing *(s{e LER 83-Oll).

I l

a I

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. =: = - -.. a a..

=..=:

v 1.

Hase of Facility:

Three Mile Island Kuclear Statien, Uni 1 2.

Scheduled date for next refueling shutdcrn:

Unkncvn 3

Scheduled date for restart fc11oving refueling:

Unknown L.

L'ill refueling or resu=ption of operation thereafter require a technical specification change or other license a:endment7 If answer is yes, in general, what vill these be?

If answer is no, has the reload fuel design and ccre ecnfiguraticn been revieved by your Plant Safety Reviev Oc=ndttee te determine whether any unrevieved safety questions are assceiated with the core relcad (Ref. 10 CFR Section 50 59)7 If no such review has taken place, when is it scheduled?

Amendment Mc. 50, cycle 5 reload, was a;;reved en 7c.

5 Scheduled date(s) fer sutritting proposed licensing ac:ien and su;;crting infor ation:

N/A 6.

Important licensing considerations associa:si vith refueling, e.g. new or different fuel design or supplier, unreviewed design er perfermance analysis methods, significant changes in fuel design, new crerating procedures:

n/A 7

The number cf fuel assenhlies (a) in the ecre, and s :

in -he s;er; duel s:crase pocl:

(ci

-47 (b) 206 8.

The present licensed spen fuel pool s:crage :a;a:i:: snd he size :f any increase in licensed stcrase capaci::t ths: har teer requested er is planned, in nudber cf fuel asse:blies:

The present licensed capaci;y is T52. There are n: pisnned increases at this time.

c.

The prclected date cf the last refuelin

'.a enn :e discharcei :c the :;en; e

fuel pool assuming the prescn: licensed ca;a:i :-

10E 7 is the lar refueling discharge which all: : ful ::re :ff-icad capacity (177 fuel asseiblies).

OPERATING DATA REPOF.T DOCKET NO.

50-2E9 DATE May 13. 1983 COMPLETED BY C. W. Smyth TELEPHONE / 7' 7T m Rs W OPEll4 TING STATL,1 Three..ile Island Nuclear Station, Uni: I

1. Unit Name:

2. Reporting Period:

Aoril. 1983 2535

3. Licensed Thermal Power (MW ):

671

4. Nameplate Rating (Gross MWe):

819

5. Design Electrical Rating (Net MWe):

- 6. Maximum Dependable Capacity (Gross MWe): {0 e/6

7. Maximum Dependable Capacit) (Net MWe):

S. If Changes Occur in C:pacity Ratings (Items Number 3 Through 7) Since Last Report. Gis e Reasons:

9. Power Level To Which Restricted,If Any (Net MWe):

10. Reasons For Restrictions. If Any:

This Month Yr..to.Date Cumulatise 719.~

2879.

75912.

11. HoursIr. Reporting Period 0.0 0.0 31731.E

12. Number Of Hours Rea,etor Was Critical 0.0 0.0 839.$

33. Reactor Reserve ShutdowTi Hours 0.0 0.0 3115D. 9

14. Hours Generstor On.Line U*U 0.0 0.0

15. Unit Reserve Shutdown Hours

-0.0 0.0

76532071,

16. Gross Therma! Energy Generated (MWH)

O.

v.

zao.,;3v.

17. Gross Electrical Energy Generated (MWH)

'#0

• 23*

IS. Net Electrical Energy Generated (MWH) 0*O U*C 41.1

19. ' Unit Senice Factor U*U U*V 41.1

20. Unit Availability Factor 0.0 0.0 40.1

21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 38.3

22. Unit Capacity Factor (Using DER Net, 100.0 100.0 54.5

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Next 6 Months (Type.Date.and Duration of Eschi:

25. If Shut Down At End Of Report Period. Estimated Date of Startup:

26. Units in Test Status (Prior to Commercial Operation):

Forecast Achiesed INITI AL CRITICALITY INITIAL ELECTRICITY COMMERCI AL OPER ATION g o ;- -

f 9

' AVERAGE D A!LY L* NIT POWER LEVEL, 4

DOCKET NO.

50-2E9 U ~I L' NIT DATE COMPLETED BY C. W. Smyth (717) 948-8551 TELEPHONE A ril, 1983 P

MO.m _

DAY AVERAGE DAILY POWER LEVEL -

DAY AVERAGE DAILY POWER LEVEL (Mhe-Net) g gw,,y,,

I 9

17 0

0 2

0 is 0

3 0

39 0

4 0

20 0

5 0

21 0

6 0

22 0

7 0

23 g

0 o

74 0

0 9

25 0

i 10 26 0

0 11 0

12 25 0

13

9 0

0 14 30 0

0 15 33 g

~16 0

4 4

4 i

r

r 50-289 UNIT SilU1 DOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT N AME

'l il l -l DATE May 13. 1983 REPORT MONT11 April, 1983 COMPl.ETED RY C. W. Smyth TELEPflONE (717) 948-8551 e.

3 -,, 5 E

=

c.

5

?5b Lic "$r 9,

l, Cause & Corrective N"-

D' ' '-

"9-M

.is ; a:

Event u?

q Action to

$E E

jis j Rcroit*

N0 fU Prevent Recurrence 6

83/04/01 p

D 1

N/A ZZ ZZZZZZ RcRulatory Restraint Order 744 1

I 2

3 4

1 I'..ii cil I;cason +

McIluul:

Exhi!>it G. Instructions S-S< licilnicil A l'iinipment I-ailme (1.splain) l-Manual for Prepair. ion of Data ll Maintenani c i.i t est 2 Manual Scrain Entry Sucets for I.icensee

(-Itelncling 3 Automatic Scram.

I! vent Report (l.I:lt1 File (NilRI:G-D Rcrnla'"r> lle'l'itti"n 4-Ollies (Explain) 0161) 1: Opciasoi Is.iining & 1 it ense l'xamination

~

If Adniinisteatr.'c G Opet aljntial I e roi (l'splain)

Exhibit I - S.une Somcc I

11 OiticefI'$rl uni t

y t

OPERATIONS SISB:ARY The unit was shutdown the entire month by order of the NRC.

Core cooling was provided by the Decay Heat Removal system.

MAJOR SAFETY RELATED MAINTENANCE During the month restart modifications continued and the following major maintenance items were performed.

The Once Through Steam Generator (OTSG) Repair Program continued in the month of April with the completion of tube plugging, felt plug free path-ing and drip testing of the "A" Generator.

"B" Generator work activities l'

consisted of felt plug free pathing, eddy current testing and a second

' drip test. Work activities on both Generators will continue into the month of May.

The Pressurizer Valve Inspection Program continued with the inspection pro-Sram completed and the reassembly of valves RC-RV-2 and RC-V-2.

The in-spection work included UT of studs and x-ray /PT work on valve parts. These inspections were performed with satisfactory results. The reinstallation of valve-RC-V-1 was completed with the welding in of the leak off piping.

The Pressurizer (RC-T-2) inspection was co=pleted during the month with an internal camera inspection, canned entry for visual. inspection and swipe samples, hydrolasing and a follow up camera inspection.

Remote ultrasonic testing was performed on various internal welds. Magnetic particle and visual inspections were performed on the manway studs.

All inspections were performed with satisfactory results.

The manway cover was reinstalled completing this work.

Waste Gas Disposal System work continued-during the month with the completion of diaphragm changeout of system valves.

Repairs to relief valve WDS-V-12 are in progress. A satisfactory pneumatic leak test was performed on WDG-V-4 and WDG-V-158.

The Snubber Testing Program was completed during the month with the following snubbers removed, repaired, tested satisfactory and reinstalled. MS-209 failed to lock up.

See report LER 83-012.

PR-26 FN-111 EF-85 BS-26A FW-110 BS-23 MS-209 MUE-43 BS-24 MS-211 MS-206 PR-37 MS-219 FW-112 SPSE-2 ES-27 MS-222 BS-22

' Air Handling System purge valve seat replacement work was completed during the conth of April with new seats installed in valves AH-V-1A and AH-V-lC.

Local Leak Rate Testing of these valves were perforred satisfactorily.

Decay Heat Removal pump DH-P-1A repairs were completed during the month with reassembly of pump internals, motor / pump coupling align =ent and satisfactory testing'(see LER 83-011).

3 i. '

T 1-O..._?*u*_*T_ *". *:__.. P... :C t..t.r.A9.-*. * *.*=.ll._=,*

• M.

1. :I!ame.of Tacility:

-r C

9(

~7 Three Mile Island liuclear Station, Unit 1 2.

Scheduled' date for next refueling shutdcrn:

Unkncvn-3.

Scheduled date for restart following refueling:

Unknown.

h.

Uill refueling or resumption of ' operation theree.fter require a technical

- specifice. tion change or.other license amendnent?

i-If. answer is yes, in general, what vill these be7 4

If ansver is no, has the reload fuel design and ccre ecnfiguraticn been reviewed by your Plant' Safety Revier Cc=.ittee to dete=ine whether any unrevieved safety questions are e.ssceiated with the core relcai (Ref. 10 CFR Section 50 59)?

If 'no such reviev has. taken place, when is it scheduled?

Amend =ent lic. - 50, Cycle 5 reload, was approved en 3-16-79 5

Scheduled date(s) ' for sutritting proposed licensing e.cticn-e.nd s;;;crting

' infernaticn:

I;/A 4i L

6.

Important licensing considerations associated vith refueling, e.g. new cr different, fuel design er su*cplier, unreviewed design or perfersance -

analysis methods, significant changes in fuel design, new crere. ir.g i

procedures:

1;/A

- 7.'

~The nunber cf fuel assentlies (a) in the ccre, and ':. in the sien: fuel t

s:crace noc1:

- e y

r.s 2--

s)

-st

.(b)' 205 E.1The present licensed spen; fuel poc1 s:crage -capacity and the sice cf e.ny increase in licensed stcrase capaci:7 that hs.s tet - recuestei cr is pie.nned,-lin nu=ter cf' fuel assemblies:

The present licensed capacity is 752.

There e.re n: planned increases at this time.

c.

The projected date cf the last refueling thac cr.: le dicch:-rgei c th c;:::

fuel pool. assuring the presen licensei capacity-

19E7 is he last refuelin; discharge which al'cvs ful'. ecre ff ~cai capacity-(1~T fuel e.sse:blies).

1

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