ML20149H100

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Monthly Operating Rept for Jan 1988
ML20149H100
Person / Time
Site: Davis Besse 
Issue date: 01/31/1988
From: Cipriani J, Storz L
TOLEDO EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
KB88-00092, KB88-92, NUDOCS 8802190109
Download: ML20149H100 (6)


Text

o OPERATLNG DATA REPORT DOCKET NO. _50-346 DATE - 2ilW COMPLETED BY 1 cieriani TELEPHONE JL2.h.1, OPER4 TING ST ATUS

1. Unit Name:

MVi'-Pe"* l' nit I N '"

2. Reporting Penod:

Januarv 1"A

3. Licenwd Thermal Power (M%ti:

2772 925

4. Nameplate Rating (Grou Mhen.

$. Design Electrical Rating (Net Mhe): 90h

6. Mastmum Dependable capacity (Grom Mkel-90' 860
  • Masimum Depend.ble Capacity (Net Mwe):
6. If Changes Occur in Capacity Ratings (ltems Number 3 Throbeh 7)Since Last Report.Give Reasons:
9. Power Lesel To khich Restricted.lf A 3 (Net Mwe):

continued at 81 percent

10. Reasons For Restrictions. lf Any:

b n-rn the re-nval of evn and the racetne of a third : ain steam safetv valve on October 10 1987.

This Month Yr,to Dete Cumulatise 11 Hours in Reportmg Penod 744 744 83.400

12. Number Of Houn Reactor Was Cntical 744 744 44.224.s
13. Reactor Rewne Shutdown Hour, o

o 5.050.1

14. Hours Generator On-Lin, m.5 663.5 42.464.5 o

0 1.132.5 l$. Urut Rewne Shutdown Houn

16. Grom ThermalinerTy Generated (M%H) 1.465.612 1.*e5.e12 99.427.811 l* Grou Electrical Energy Genersted (MhH) 473.000 473.006 32.846.603 15 Net Electrical Energy Generated (M%Hi 440.865 440.655 30.741.532
19. Unit Senice Factor 89.2 89.2 50.9
20. Umt 4*ailabihty Factoe 89.2 89.2

$3.0

21. Unit Capacity Factoe (Uning MDC Neti 68.9 68.9 42.9
22. Unit Capacity Factor (Uung DER Net) 65.4 65.4 40.7
23. Unit Forced Outage Rate 0

0 32.9 -

24. Shutdouni Scheduled Oser Nest 6 Months (Type. Dete.and Ducation of Eacht:

Refueline - Start on March 11, 1988. 26 veeks - End on September 9. 1958 f

l 2$. If Shut Down At End Of Regert Period. Estimated Date of Startup:

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26. Units in Test Status iPnot to Commereal Operation)

Forecast Achiesed INITI A L CRITIC ALITY INITl4 L ELECTRICITY COMMERCI AL OPER 4 TION h

9802190109 890131 FDF ADOCN 05000346 to/77 6 R

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  • / A N/A N/A Th Turbanc was taken off line due to m in Turbine Torsion.el Test. but the reactor stayed critic;st.

3 Fr Forced Deemens peethods

'yehlbst C - Isotractione for FrePeretten of Dess St Scheduled A-Equiposet Feilere (Emplete) 3-see eet yeary Sheete for Licensee Tweet SePart (LE81 s-seeietseasice er Teet 2-eeen.e1 Seaem pt1e (wvefC-OI61)

C-set.ettag 3-a.nemet te sc ree D-eeg letery meetriction 4-Centlemetten from I.htbit 1h Searce E-eperater frateleg & t.teense Eme=teetten Fr.,te peneth t

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(roeve) and Freeeweteer Code Saf ety vetwee (FC5ve) tidtther (Emplete)

AVERAGE D41LY UNIT PO%ER Ltygt DOCKET NO.

50-346 LWIT Davis-Besse t' nit 1 D4Tg 2/12/88 C04PLITfD sy

_J. Cipriani TELEPHONE __ X7365 MONTy January 1988 D4Y AVER 4GE D4fty Powgg (gygg DAY AYER ACE DAILY Powgg tgygt (Whe Net) iMWe Net) j 695 gy 2

696 61 18 3

696 400 j,

4 696 666 20 693 21 636 696 6

22 689 7

696 23 6R8 g

e97 24 638 9

700 25 689 10 700 26 689 699 lg 689 27 I;

695 28 688 699 3

29 685 692 g4 684 M

73 33 682 33 16 f

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j OPERATIONAL

SUMMARY

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January 1988 i

The reactor power vas maintained at approximately 81% power untti 0548 i

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hours on January 15, 1988 vhen reactor power was reduced to approximately i

121 to perform the Main Turbine Torsional Test.

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The turbine generator vas synchronized on line at 1420 hours0.0164 days <br />0.394 hours <br />0.00235 weeks <br />5.4031e-4 months <br /> on January 18, i

1988.

Reactor pover is limited to approximately 82%. This power level limitation t

is a result of removal of two Main Steam Safety Valves and the gagging a j

third of Main Steam Safety Valve SP17B5.

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_,___.___.___..__.__,.___.___.___._.______.__..____..,I

P I

REFUELING INFORMATION Date:

January 198,8 1.

Name of facility:

Davis-Besse Unit 1 2.

Scheduled date for next refueling outage? March 1988 3.

Scheduled date for restart following refueling:

September 1988 4.

Vill refueling et resumption of operation thereafter require a technical specification change or other license amendment? If ansver is yes, vhat in general vill these be? If ansver is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Reviev Cor.mittee to determine whether any unrevieved safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?

Ans:

Expect the Reload Report to require standard reload fuel design Technical Specifications changes (2. Safety Limits and Limiting Safety System Settings, 3/4.1 Reactivity Control Systems, 3/4.2 Power Distribution Limits and 3/4.4 Reactor Coolant System.)

5.

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

March 1988 6.

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

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

1.

The highly absorbing silver-indium-cadmium axial pover shaping rods vill be replaced with reduced absorbing inconel rods.

2.

The discrete neutron sources vill be removed from the cote and not replaced.

7.

The number of fuel asse-blies (a) in the core and (b) in the spent fuel storage pool, and (c) the nev fuel storage areas.

(a) 177 (b) 204 - Spent Fuel Assemblies (c) 64 - New Fuel Assemblies 8.

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

Present:

735 Increased size by:

0 (zero) 9.

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

Date:

1995 - assuming ability to unload the entire core into the spent fuel pool is maintained

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tot t 00

%ss EDISON February 12, 1988 KB88-00092 Docket No. 50-346 License No. NPF-3 Document Control Desk U. S. Nuclear Regulatory Cor. mission 7920 Norfolk Avenue

Bethesda, MD 20555 Gentlerent Monthly Operating Report, January 1988 Davis-Besse Nuclear Pover Station Unit 1 Enclosed are ten copies of the Monthly Operating Report for Davis-Besse Nuclear Fover Station Unit I for the month of January 1988.

If you have any questions, please feel free to contact Bilal Sarsour at (419) 249-5000, Extension 7384.

Very truly yours, s,'

,/

/

Louis F. Stor:

Plant Manager Davis-Besse Nuclear Fover Station

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LFStGAGtECCtBMStjeh Enclosures cci Mr. A.

Bert Davis, v/l Regional Administrator, Region III Mr. Paul Byron, v/l NRC Resident Inspector Mr. A. V. DeAgazio SRC Project Manager 9

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