ML20080P817

Monthly Operating Rept for Jan 1984

ML20080P817
Person / Time
Site:	Crane
Issue date:	01/31/1984
From:	Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP.
To:	Mcdonald W NRC OFFICE OF ADMINISTRATION (ADM)
References
5211-84-2040, NUDOCS 8402230129
Download: ML20080P817 (11)

Text

_

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OPERATING DATA REPORT y

f DOCKET NO.

50-289

~~

DATE February 15, 1984 COMPLETED BY C. W. Smyth TELEPHONE (717) 948-8551

-OPERATING STATUS NOTES

1. UNIT NAME; THREE MILE ISLAND UNIT 1

2. REPORTING PERIOD:

JANUARY

,1984.

~~3.

LICENSED THERMAL POWER (MWT):

2535.

4.' NAMEPLATE RATING (GROSS MWE):

871.

5.~ DESIGN BLECTRICAL RATIN_G__(NET MWE)_:

8.lb 3.-MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):

824.

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):

776.

, 8.__ IF CHANGES OCCUR IN__LITEMS_3-7 ) SINCE._LAS.T._ REPORT, GTVE_ REASONS

• __L._ LOWER _ LEVEL _.TO_WHICH_ RESTRICTED _IE_ANY. 4 NET _.MWE )

10. RCASONS FOR RESTRICTIONS, IF ANY:

~

THIS MONTH YR-TO-DATE CUMMULATIVE 11.' HOURS IN REPORTING PERIOD 744.

744.

82537

12. MUMBER OF HOURS REACTOR WAS CJLI._TICAL 0_0 n.n 31731,g

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 838.5

14. COUPS GENERATOR ON-LINE 0.0 0.0 31180.9

15. UNIT RESERVE SHUTDOWN HOULS n.0 0.0 0.A

16. GROSS THERMAL ENERGY GENERATED (MWH).

O.

O.

76531071.

27. GROSS ELECTRICAL ENERGY GENERATED (MWH)

O.

O.

25484330

ly. NET ELECTRIOL ENERGY. GENERATED __(MWR).

0...

Q.

93840053.

!19.. UNIT SERVICE FACTOR 0.0 0.0 37.8

'E UNIT AVAILABILITY FACTOR 0.0 0.0 37.8 j h UpIT CAPACITY FACTOR (USING MDC NET) 0.0 00

~46.S 2%. UNIT CAPACITY PACTOR (USING DER NET) 0.0 0.0 35.3

L.' UNIT FORCED OUTAGE RATE 100.0 100.0 58.6

~

~

U..

SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH 3$. 1F SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

8402230129 840131 PDR ADOCK 05000269 R

PDR

I _'.

.2

_2..

._...-me-e.--~_-

~~*

s AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-289 UNI'"

TMI-1 DATE February 15, 1984 COMPLETED BY G. W-Smyth TELEPHONE (7;7) 948-8551 l

MONTH:_ JANUARY.

DAY-_-_ AVERAGE _ DAILY POWER LEVEL DAY-AVERAGE-DAILY-FOWER-LEVEL-

- (MNE-NET)

(MWE-NET)

O.

17 0

9_.

n.

18 n.

3 0

19 0

4-O.

20 0

5__.

-0..-

2L

-. -_.S.

6 0

22 0.

7 0

23 3

1.

8

. _ _ _ _ _0.

24 n;

9 0

25 O.

10 0

26 0

_11...- _. _.. _.. _ _ __ _ _ 0. _, _ _

2.7__ -

O.

12 0.

28 0.

13 0

29 0.

14. ____ _____._,0.

_30 0,

15 O.

31 0

16 0

t N.+

a.eed.*4 M.

me==

mm>.

,pg e-4..ui-6

.ewewa*.---th es.am

>-..---_.s-.

ram e p

.me,-

,w~

w...a-e c.-.

=w

- - - - +

e

+

W-d n,,,.m.

m.e-

.s.e

• r

-*-'W.'-*'"

Ne'*8'"

NRC MONTHLY REPORT - JANUARY 1984 The Unit remained in cold shutdown the entire month by order of the NRC.

Core cooling was provided by the Decay Heat Removal System.

A Reactor Coolant pump was run tne majority of the month except as in-dicated below.

A bubble was maintained in the pressurizar and RCS pregsure was maintained at about 310 psi, and temperature at abouc 130 F.

The sc.condory side was in partial wet layup with the steam lines drained.

A vacuum was maintained on the secondary side for most of the month.

On. Tuesday, January 31 vibration readings on the run-ning Reactor Coolar.t pump (RCP-lD) increased unexpectedly from about 8 mils to about 28 mils.

The pump was secured and we maintained the primary without forced flow the remainder of the month.

Investigations and repair work on the RCP will be reported next month.

MAJOR SAFETY RELATED MAINTENANCE Building Spray Pump (BS-P-1B)

Repair work reported last month was completed with reassembly of the pump, coupling, and satisfactory ISI testing.

Seal _ Injection Filter (MU-F4B) Repairs After identifying a closure plug leak, the seat area was lapped.

Pre-parations were being made at the end of the month to rebuild the seat area with Belzona Molecular compound.

+

r 50-289 DOCKET NO.

UNIT SilOTDOWNS AND POWER REDUCTIONS UNIT NAME '1111 - 1 DATE February 15, 1984 COMPLETED ItY. _th_W. Smyth REPORT MONTH acauary, 1984-TELEPHONE (717) 948-8551 I

"L

_.c

=

r, 5 u>.:

E Caine & Corrective l

,E-t, 8%

2E E

7.s ;;;

Licensee

y 3

Action to Date 9,

3g jg5 Event

$E 5

j5g Re;xtri n

- tN 0 O

prevent Recurrence 6

Regulatory Restraint Order 1

84/01/01 y

744 D

1 N/A ZZ ZZZZZZ I

2 3

4 l'. Fo< ccil Itcason:

Methml:

Exlubit G - Instructions 5: Scheduled A-l'quipment Failure (i.xplain) l-Manual for Preparatica of Data ll-Maintenance of Test

2. Manual Scram.

Entrv Sheets for 1.ieensee C-Refochng

.b Automatic Sci.im.

Event Itepori *l.I:III File (Nilit!'G-D-Itegulatory itestritrion 4-Other (lixplain) 0161)

E-Operator Tiaining A 1.icense IIxamination 5

F-Administrative Exhibit I S.une Sour e G-Operatjonal Eu ros (lixplain)

II Other iII xplain)

EI~2.'_:50 :::F F."._AT:O" EI;'JIS.T_

1.

Nate of Facility:

Three Mile Island Nuclea-Station, Unit 1 2.

Scheduled date for next refueling shutdown:

l Unknown 3

Scheduled date for restart following refueling:

Unknown h.

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

If ensver is yes, in general, what vill the: e be?

If answer is no, has the reload fuel design and cere configuraticn been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?

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

Amendment No. 50 Cycle 5 reload, was approved on 3-16-79 i

5 Scheduled date(s) for submitting proposed licensing action and suppcrting information:

N/A o.

Important licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or perferrance analysis nethods, significant changes in fuel design, new operatftg procedures:

N/A 7

The number of fuel assembliec (a) in the core, and (t) in the spent fuel storage pool:

(a) 177 (b) 208 6.

The present licensed spent fuel poc1 stcrase capacity and the sice cf any increase in licensed storage capacity that has been requested cr is planned, in number of fuel assemblies:

The present licensed capacity is 752. There are no planned increases at this time.

o.

The projected date of the last refueling that can be diccharged to the spent fual pool assuming the present licensed capacity-1988 is the last refueling discharge <tich c11cvs full core Off-Icad capacity (177 fuel assemblies).

OPERATING DATA REPORT DOCKF" NO.

50-289 f

nA7p Februarv 15. 1984 COMPLETED BY C. W.

Smvth TELEPHONE (717) 948-8551

[_

t OPERATING STATUS

(

f m. __.

NOTES ll 1. UNIT NAME:

THREC MILE ISLAND UNIT 1 I 2. REPORTING PERIOD:

JANUARY

.1984.

3. LICENSED THERMAL POWER (MWT):

2535.

4. NAMEPLATE RATING (GROSS MWE):

871.

5. DESIGN _ ELECT _RICAL RATING (NET _.MWE) :

812..

_6. MAXIMUM DEPENDABLF: CAPACITY (GROSS MWE):

E24,

7. !OXIMUM DEPENDABIO CAPACITY (NET MWE):

776..'

8e IF CH ANGES OCCUR _IN ('IEMS.__3-7_)_EINCE_.LAS.T__. REPORT. cTVn REMONS e

___9 __EOWER_LEVEIu.TO_WHmIC1LRESTRICTF% TF ANY ( MET __MWE }

10. REASONS FOR RESTRICTIONS, IF ANY:

~

THIS MONTH YR-TO-DATE CUMMULATIVE

11. HOURS IN REPORTING PERIOD 744 744.

82537 12, NUMBER OF HOURS REACTOR WAS_C_P._T_I_CA.L 0_0 n.n 31731;o II 1

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 83P.5

14. HOURS GENERATOR ON-LINE 0.0 0.0 31180.9

15. UNIT RESER.VE. SHU rDOWN, HOURS __

_Q.0 0n 0.n

16. GROSS THERMAL ENERGY GENERATED (MWH)

O.

O.

76531071.

17. GROSS ELECTRICAL ENERGY GENERATED (MWh)

O.

O.

25484330.

.13, KET ELECTRICAL _ ENERGY. GENERATED __(MWH)..

A Q.

.23 8 4 0 053.._.._ -

19. UNIT SERVICE FACTOR O.0 0.0 37.8 20 UNIT AVAILABILITY FACTOR 0.0 0.0 37.8 23*___U!JIT CAPACITY _ FACTOR (PSIN.G MDC NET) 0.0 0.0

_36.9

22. UNIT CAPACITY FACTCR (USING DER NET) 0.0 0.0 35.3

23. UNIT FORCED OUTAGE RATE 100.0 100.0 58.6

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONT9S (TYPE, DATO, AND DURATION OF EACH

25. IF SHUT DOWN AT END OF REPORT PER7.OD, ESTIMATED DATE OF STARTUP:

-~~~

g.

ag..

.,gw M

_.e

4. dum

+-e.m.

_meeEr*NP" * - * " "**

k 9

AVERAGE DAILY UNIT POWER LEVEL 3.

50-289 t

L.

T MI--l-DATE February 15, 1984 COMPLETED BY W-smyth v.

TF,LEPHONE (7;;) 93g_cn MOUTH :.___ JAN UARY

.DAL_ AVERAGE _. DAILY-POWER LEVEL DAY-AVERAGE _ DAILY-FOWER-_1,vCL (MWE-NET)

(MWE-NET) 1 0

17 0

_2--

n; 18 0,

3 0

19 0

4-O.

20 0

E n.

?1 n.

6 0

22 0.

7 0

23 0

~

8_

0-

?a n;

9 0

25 O.

10 n.

26 0

.. 11

_._ _... _. 0. _m 27 0.

12 0

28 0.

13 0

29 0.

_ _. _ _.... 14__

_.___ 0.

3n n;

15 0

31 0,

16 0.

--..--.e..m.-

• * ~ ' " " '

h

,,m,.

p

-e e.

.6eee-eehNN"_ M Ne, ae.,m

.e 9

um.ey w.

.e.,._mmm----e.ewme

-_.M

- =_..

-ee-m

- =. - * - +

,g, e

a em e+e.

e-.-e mm--Mv_@-*-*-*e66* * ' " ' " " - * * * *

.... i.... _.

/

NRC MONTHLY REPORT - JANUARY 1984 The Unit remained in cold shutdown the entire month by order of the NRC.

Core cooling was provided by the Decay Heat Removal System.

A Reactor Coolant pump was run the majority of the month except as in-dicated below.

A bubble was maintained in the pressurizer and RCS preg 3ure was maintained at about 310 psi, and temperature at about 130 F.

The secondary side was in partial wet layup with the steam lines drained.

A vacuum was maintained on the secondary side for most of the month.

On. Tuesday, January 31 vibration readings on the run-ning R2 actor Coolant pump (RCP-1B) increased unexpectedly from about 8 mils to about 28 mils.

The pump was secured and we maintained the primary without forced flow the remainder of the month.

Investigations and repair work on ?.he RCP will be reported next month.

MAJOR SAFETY RELATFD MAINTENANCE Building Spray Pump (BS-P-1B)

Repair work reported last month was completed with reassembly of the pump, coupling, and satisfactory ISI testing.

Seal Injection Filter (MU-F4B) Repairs After identifying a closure plug leak, the seat area was lapped.

Pre-

~

parations were being made at the end of the month to rebuild the seat area with Belzona Molecular compound.

P 9

e 50-289 DOCKET NO.

UNIT SliUTDOWNS AND POWER REDUCTIONS UNIT NAM E ' TM L-l

F DATE February 15, 1984 COMPLETED BY C. W. Smyth REPORT MONT11 January, 1984 TELErilONE (71h 948-8551

.5 E 3

.I Licensee 5-t, Cause & Corrective W.

Date R

3@

.S s 5 Event r,. 7 E3 Action to l

$E 5

3 di g Report s,

,# v

$U Prevent Recurrence H

u O

Reguintory Rer,traint Orcier 1

84/01/01 F

744 D

1 N/A ZZ ZZZZZZ i

1 i

2 3

4 Methoti:

Exhibit G Instructions l': For t cil Reamn:

l-Manual for Preparation of Data S Stheduled A.liguipment Failure (lixplain) it. Maintenance of Test 2 M.mnal Scrarn.

lintry Sheets for 1.icensee

3. Auf omatic Scram.

Event ReporI (1.l:R) File tNtIRI'G-C-Ref ueling 1). Regulatory Restriction 1-Other (lixplain) 0161)

I!. Operator Training & 1.icense Examinalit,n 5

F.Athninist rative Exhibit 1 - Same Souru G-Operatjunal Ee ror (I.xplain) ll-Ot her liixplain)

L p

'~

w... -.._-_-

- au.

a.

=. :-

/

- 1.

.Ha=e of Facility:

Three Mile Island Unclear Station, Unit 1

'2.

Scheduled date for next refueling shutdown:

Unknown

' 3 Scheduled date for restart following refueling:

Unkncvn

~ h.

Will refuel $ng or resumption of operation thereafter require a technical specificat$an change or other license amendment?

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

If answer is no, has the reload fuel design and ccre configuration been reviewed by your Plant Scfety Review Connittee to deternine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50 59)?

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

Atendment No. 50, Jycle 5 reload, was approved on 3-16-79

-c 5

Scheduled date(s) for suh=itting proposed licensing action and supperting information:

.N/A c.

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

N/A T.

The nunber of fuel assenblies (a) in the core, and (t) in the spent fuel stcrage pool:

o

~

(a) 177 (b )'

208 8.

The. present licensed spent fuel poc1 storage capacity and the size of any increase in licensed storage capacity that has been requested er is planned,'in number of fuel cssemblies:

The present licensed capacity is 752. There are no planned increases at this time.

9~.

The projected date of the last refueling ths: can be discharged to the spent fuel. pool assu=ing the present licensed capacity:

1988 is the last refueling discharge which allevs fc11 ccre eff-1cai

. capacity (17T fuel assentlies).

s i

F'/,.

Nuclear GPU Nuclear Corporation 5

,ome::;48o s

Middletown, Pennsylvania 17057 0191 717 944-7621 TELEX 84 2386 Writei s Direct Dial Number:

February 15, 1984 l

5211-84-2040 I

Office of Management Information and Prograra Control Attn:

W. C. Mcdonald c/o Distribution Services Branch DPC, ADM U. S. Nuc'aar Regulatory Commission Washington, 3.C.

20555

Dear Sir:

Thrc.e Mile Island Nuclear Station, Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 January lionthly Operating Report biclosed please find two (2) copies of the January Operating Report for Three Mile Island Nuclear Station, Unit 1.

Sincerely, I. D. Hukill Director, TMI-l llDil:vj f Enclosures cc:

V. Stello Dr. T. E. Murley GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation k'