ML20079F978

Monthly Operating Rept for Dec 1983

ML20079F978
Person / Time
Site:	Crane
Issue date:	12/31/1983
From:	Hukill H, Smyth C GENERAL PUBLIC UTILITIES CORP.
To:	Macdonald W NRC
References
NUDOCS 8401190372
Download: ML20079F978 (6)

Text

OPEPITING DATA-REPORT s

DOCKET NO.50-20c

.__. DATE._ Januarv 13, 1984--

CpMPLETED BY C. W. Smyth _

TELEPHONE (7171 948-8531 OPERATING STATUS f NOTES

1. UNIT NAME:

THREE MILE ISLAND UNIT 1 l

=2.e. REP.ORTING PERIOD :__.

DECEMB.E R_,1.9.8 3.. _l..__.

3. LICENSED THERMAL POWER (MWT):

2535.

4. NAMEPLATE RATING (GROSS MWE):

871.

5. DISIGN_ ELECT.RICAL__ RAT.IN_GDET MWE1 e 81_9_.

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):

824.

7 MAXIMUM DEPENDABLE CAPACITY (NET MWE):

776.

_8..

IF CHANGES OCCUR IN (_I.TEMS.3-7_.)_S.INCE LAS.T_REEQRT,__GJ3IE__8EASONS :

__ 9. POMER LEVEL TO WHTCH RESTRICTED. TP ANY (NET MWPi

10. REASONS FOR RESTRICTIONS, IF ANY:

(

r THIS MONTH YR-TO-DATE CUMMULATIVE 744.

8760 81793.

11. HOURS IN REPORTING PERIOD 0.0 0.0 31731.R 1?. NUMBER OF HOURS _EEACTOR WAS CRITICAL 0.0 0.0 838.5

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 31180.9

14. HOURS GENERATOR ON-LINE 0.0 0.0 0.0

15. UNIT RESERVE SHUTDOWN HOURS 0.

---0.---

76;31001. --

16. GROSS THERMAL ENERGY GENERATED (MWH)-

17. GROSS ELECTRICAL ENERGY GENERATED (MWH)

O.

O.

25434330

,18. NET ELECTRICAL ENERGY GENERATED (MWR)

O.

O.

23840053.

0.0 0.0 38.1 119. UMIT SERVICE FACTOR 0.0 0.0 3R.1 s20 UNIT AVAILABILITY FACTOR nn n_n 22,9 91_ imTT CAPACTTV FACTOn (11RTNO MDr MPTi

'22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 0.0 35.6 100.0 100.0 58.2

. 23. UNIT FORCED OUTAGE RATE

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION O

' 2 5.

IF SHUT DOWN AT END OF REPORT PERIOD, ESTI!!ATED DATE OF STARTUP:

y.

.W.m.

.e s

B401190372 831231 PDR ADOCK 05000289 R

PDR

2 AVERAGE DAILY Ut1IT POWER LEVEL DOCKET NO.

50-289

.U121*

T ". I - 1..

(

DATE Januarv 13, 19_84 COM.PLETED BY C. W. Smyth

[

'%E P11CI'.E__( 717 ) 948.-8551 - -

[.

MONT_H:_ _ DECEMBER _

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DA RY POWER _!~ VEL (MWE-NET)

(MWE-NET) 1 0

17 0

2

___0 18 0.,

3 0

19 0

r 4

0 20 n.

5 0.

21 n..

6 0.

22 0.

[

7 0,

23 n.

8 0.

24 0.

9 0

25 0

10 0

26 0,

11 0.

27 0.

12 0.

28 0

> f:

13 0

29 0

14 0.

30 n.

15 O.

31 0

16 0,

e

.f 50-289

~

UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. -

UNIT N 4ME

,I M I DATE January 13, 1984 REPORT MONTil na,amhar-1983 ey_Smyth TE I

t 3

g"L c

re 3 u, =

.2 _e g

,.s X Licensee E*

Cause & Corrective g ~8 No.

Date g

3g

,g 5 5 Event u,2 a

Action to c3 E 5

j@g Report,,

,# G u

Prevent Recurrence 6

1 83/12/01 F

744 D

1 N/A ZZ ZZZZZZ Regulatory RestrnInt Orcier l

2 3

4 l-I 'o s teil 1(cason :

Methml; Exhibit G -Instructions S Sc hetinicil A.Frinipment Failure (Explain) l-Manual for Pseparation of D.ita 11-Maintenance or' Test 2-Mannal Scram.

Entry Sheets for 1.icensec C-Iterneling 1 Automatic Scram.

Event 1(cport (1.1 R) Eine (Nill (I G-D Regniatory Restriction 4 Other (Explain) 0161) 1 Operator Training & l.icenw ITamination I Atiministrative 5

G Operatjonal Frror (ISplain)

Exhibit 1 Sarne Source II Ot hes.(ISplain) e

s s

OPERATIONS

SUMMARY

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

Core cooling was provided by the Decay Heat Removal System.

MAJOR SAFETY RELATED MAINTENANCE The following work was performed during the month:

Snubber Inspection Program:

Work that was generated as a result of an in-depth inspection of all "important to safety" snubbers, was completed last month.

In addition to all of the minor repairs made, approximately 20 of the snubbers were totally rebuilt and tested satisfactorily.

Main Stream Safety Relief Valves:

The remainder of the 14 relief valves that had been identified to be weeping during Hot Functional Testing were repaired. This consisted of disassembly, lapping seats and reassembly.

OTSG Work:

The manway and handhole nuts were retorqued on both CTSGs. Two studs that exhibited boron crystalization were removed and inspections were performed to detect both thread wastage and intergranular stress corrosion cracking of thi carbon steel studs. No wastage or cracking was observed and the studs were replaced. The remaining studs with lesser deposits were cleaned and lubricated prior to the final torquing..

Decay Heat Cooler IB Inspection:

'Because of poor decay heat removal capacity during the last Hot Functional Test, OH-C-1B was inspected (shell side). No fouling was identified. As part of the investigation, the cooler bypass valve (DC-V65B) was found to be partially open when in it's closed position. This valve has been disassembled and repaired.

Cooler performance will be watched carefully during the next opportunity.

If decay heat cooling capacity continues to be a problem, it will be resolved, however, the repair of the bypass valve is expected to have solved the problem.

Building Spray Pump Repair BS-P-1B repairs were necessary to replace damaged wear rings that resulted from the pump being run with the suction valve closed. Repairs and testing will be completed in January.

Makeup System Valve Repacking:

A program was conducted to repack Makeup System valves in the Aux. Building.

Also repaired were leakoff line tubing leaks and all threaded fittings.

c 1.

Care cf Facility:

I

[

Three Mile Island _Euclear Statien, Uni: 1 L

'2.

Scheduled' date for next refueling shutdcun:

Unknovn-1

[

3 Scheduled date for restart fol2owing refueling:

Unknown h.

Will refueling or resu=ption' of operation thereafter require a technical specification 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 core configuration been reviewed by ycur Plant Safety Review Concittee te 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

.o s

-+ -

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

RfA 6.

Important licensing considerations associated with refueling, e.g new or different fuel design or suppli~er, unreviewed design er perfernance analysis methods, significant changes ir fuel design, new operating

! procedures:

E/A

.The nu=ber of fuel asse=blies (a) in the core, and (t) in the spent fuel L

7 storage pool:

(a)- 177

-(b) 208 l

l S.

The present licensed spent fuel pool stcrage capacity and t're sice cf l

Eny increase in licensed storage capacity ths: has teen req;ested er i:

planned, in number of. fuel assemblies:

m n

1 The present licensed capacity is 752.

There are no planned increases o

at'this time.

9 The projected date cf the las refueling tha :an 'e discharged :: the s;ert fuel poci assuming the present licensed capsci '

1988 is-the last refueling discharge

.i ir sil:vs full ccre :ff-1:sd

.capscity (177 fuel assent;ies).

w o.

GPU Nuclear Corporation Nuclear

,omear8o Middletown, Pennsylvania 17057-0191 717 944 762*

TELEX 84 2386 Writer's Direct Dial Number:

January 13, 1984 5211-84-2009 Office of Management Information and Program Control Attn: W.C. MacDonald c/o Distribution Services Branch DPC, ADM U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Sir:

Three Mile Island Nuclear Station, Unit I (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 December Monthly Operating Report Enclosed please find two (2) copies of t.he December Operating Report for Three Mile Island Nuclear Station, Unit I.

Sincerely,

. Iukill Director, TMI-1 HDH:CWS mle Enclosures l

cc:

V. Stello Dr. Thomas E. Murley l

Y

.$klt GPU Nuclear Corporation is a subsidiary of the General Public Utliities Corporation