ML19225A790

From kanterella
Revision as of 03:48, 2 February 2020 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Monthly Operating Rept for June 1979
ML19225A790
Person / Time
Site: Pilgrim
Issue date: 07/09/1979
From: Whitney G
BOSTON EDISON CO.
To:
Shared Package
ML19225A789 List:
References
NUDOCS 7907200252
Download: ML19225A790 (6)


Text

4:

""" Edison e-m PILGRIM NUCLEAR POWER STATION RFD # 1 rocky HILL HOAD PLYMOUTH. mas 3ACHUsETrs 02360 July 12, 1979 BECo Ltr #79-141 Director Office of Managenert Information and Program Control U.S. Nuclear Regulatory Cotnission Uanhingten, DC 20555 Docket No. 50-293 License DPR-35 Subj ec t : June, 1979 Monthly Report

Dear Sir:

In accordance with PNPS Technical Specification 6.9. A.3, a copy of the Operational Status Summary for Pilgrim Nuclear Power Station is attached for your information and planning. .

Respectfully submitted, P. J. McGuire Station Manager Nuclear Operations GGH:dl cc: Director Office of Inspection and Enforcement Of fice of Nuclear Regulatory Commission U. S. Nuclear Regulatory Consission Washington, DC 20555 Director of Region I Office of Inspection and Enforce =ent U. S. Nuclear Regulatory Consission 631 Park Avenue King of Prussia, PA 19406 cc: MessrJ: J. E. Howard M. T. McLoughlin D. G. Stoodley G. C. Andognini J. A. Murphy R. Tis H. R. 3alfour J. W. Nicholson C. K. Vantrease R. A. Canalas, G.E. C. S. Ondash F. J. Wiedennann E. L. Cobb S. L. Rosen' Document Control Center Mrs. C. M. Gaffney R. J. Schug PJM (LB)

R. S. Hahn J. A. Seery M. G. Hensch R. J. Sevigny 7gg C. J. Mathis W. M. Sides JUU jn0 i6 7 9072 0 0 A fE2:

OPERATING DATA REPORT DOCKET NO. 50-293 DATE 7/9/79 CO\tPLETED llY G. G. 'Piitney TELEPflONE 1-617-746-7900 OPER ATING STATUS N '"

1. Unit Name: Pilcri'. I
2. Reporting Period; hne - 1979
3. Licensed Thermal Powei Otht): 19C8-
4. Nameplate Rating (Gross StWe). 678.
5. D: sign Electrical Ratmg (Net \tWe): 655.
6. Stasimum Dependab!e Capacity (Gross 31We): 600.
7. Stasimum Dependable Capacity (Net .\1We): 670.
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Sinte Last 1:eport. Gise Reasons:

None

9. Power Lesel To which Restricted. If Any (Net %!We): _None
10. Reasons For Restrictions. lf Any: N/A This 51onth Yr to-Date Cumalatise
11. Hours in Reporting Period 720.0 4343.0 57479.0
12. Number Of Hours Reactor Was' Critical 688.0 3791.9 40839.6
13. Reactor Reserve Shutdown liours 0.0 0.0 0.0
14. IIours Generator Or .Line 679.9 3755.3 39477.9
15. Unit Resene Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated O!WH) 1314336.0 7318090.0 65750880.0 7 Gross Electrical Energy Generated 15tWH) 452420.0 , _ ,

2515430.0 21645904.0 __

Nct Electrical Energy Generated 01% H) 435472.0 _

2420387.0 20781951.0

/. Unit Senice Factor 94.& 36.5 63.7

20. Unit Asailability Factor 94.4 86.5 63.7
21. Unit Capacity Factor (Using SIDC Net) 90.3 83.2 -

54.0

22. Unit Capacity Factor (Using DER Net) 92.3 _

85.1 55.2

23. Unit Forced Outage Rate 0.0 12.7 10.y
24. Shutdowns Scheduled Oser Next 6.\1onths (Type Date, and Duration of Each1:

Ncne

25. If Shut Down At End Of Report Period. Estimated Date of Startup: _ Cnit Operating
26. Units in Test Status (F rior to Commercial Operation): Forecast Achieved INITIAL CRITIC / .TY '

INITIAL ELECTRICITY CONI \t ERCI A L OPER ATION 366 181 mm

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-293 s

UNIT Filgrim I

. DATE 7/9/79 CO\tPLETED BY G. G. Whitnev TELEP110NE 1-617-746-7900 MONT11 June, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL

( M We-Net)

OtWe Net) 1 530. 17 6 !. .

2 63_2. 13 436.

3 A64- 19 333.

4 662. - 20 656.

5 662. 21 663.

6 6A' 5664 33 7 AA1. 23 665.

3 662. 24 663.

9 ^^* 25 663.

10 666- 26 663.

11 AAS. 27 664 12 AA4- 23 665.

13 664 _ ,9 gg4, la 661. 30 663.

15 629. 31 0.

16 1-INSTRUCTIONS On tlu., tornut. !ist t."e averag . aa,1y .ani: power !; elin \twc-Net fer each day in the repertuig 'nt.oth. Compute to the reatest who;c megawan.

N/77) 366 182

=

> C .a v

". ?

= - _

x

_ - 1 = .

ET

  • i!! 3 N em -.
i 3' +

".s

'=

o L. 6 - N T gJ = , _

m

.cy C' --

w

, .= ' u, -

3

,=

=

- ,v , , -- , ;._. .

Lt") CN O- *a. .s, .= . - -

d.* .-

,~* =

__ v e W W >= W 7=Z- E d3

~

w -. w--=

y. r. ;
    • l- m g .3 = -

~

_-=.

.==..a ~ v=,;

1 -u ;

.,L

== = . - ,. .. .,

=

v3 * , , _ O

--.- -  ; r. ,, - ,2 m~-. ~~. . . . . .=

. .= = =-

=

x= s=

, .s g

, , =

s

.=_s.

_ =

s p- - L >

,O -

3>

=

A a.-*

.J

-,= .l O%

Z 7.

m =

~ < 8=

D h

.. ~ >

.: po) 3~=

- -e. _

o lua uodwoj i j ;-

r .. .

m .

= -- = -

s

= 3 _: =- r r.s

-= = = ==

.a, = 3paj < 0a:

s, us a n e: -;

z.

.- z n

x.. s, .

m,: .

. ~

.". r=

2

- - . ,u . .

= s .c _

.- -

~

~ 2_

  • $  % .I

. e (I I .' I) O Di t

6 5t.ilin t[g n u

'.=. - .

e -n a

1 r -e. .-.-

m -s- m

.- 1.051'. 3

%) w,, -- ~dj --

3H -

~^ =a

, =_. - -

m .. =u-= w hN , - -**

($jl){Ill A

". .I

=. x

,. .- - . ~. .

LIOIICIUd y C .. =, ~.

- %_ 2._ - . = [.

, = -

= === T., a s7 = .) ?

-,2 7 ,-

f =J b 17- ,_ m-= ~-

m. - n - p 1,a .u m x%- - -v - -

N 3, ~

- c

~ ,

.- , - , =

ta *3 a %

.

- s m

-m -

2 e mm ~

L 366 183

BOSTON EDISON COMPAW PILCRIM NUCLFR POWER STATION

SUMMARY

OF OPERATIONS FOR JU':E, 1979 The station was recovering fren the snubter modification outage at the beginning of June. Reactor Pcwer was 85% on June 1 and increasing at 10MW /hr per PCICMR.

Reacter Power reached 100% on June 3, 1979 and continued at this level until June 16, 1979 except for minor power reductions to naintain main condenser delta temperature. On June 16, 1979, the unit was shutdown to replace a weeping safety relief valve and perform other planned =aintenance.

The unit was started up on June 17, 1979 and synchronized to the systen at 1613 hours0.0187 days <br />0.448 hours <br />0.00267 weeks <br />6.137465e-4 months <br />. Reactor pcwer reached 100% again on June 21, 1979 and continued at this level for the remainder of the month.

366 134

REFUELING INFOrtCION The f ollowing refueling inf ormation is included in the Monthly Report as requested in a letter to Mr. G. C. Andognini dated January 18, 1978.

For your convenience, the information supplied has been enumerated so that each number corresponds to equivalent notation utilized in the request.

1. The name of this f acility is Pilgrim Nuclear Power Station, Docket No. 50-293
2. Scheduled date for next Refueling Shutdown: January, 1980
3. Scheduled date for restart following refueling: April, 1980 4
5. Due to their similarity, requests 4, 5 and 6 are responded to collectively.
6. The fuel, which is presently expected to be loaded during the next scheduled shutdown, may be reload fuel of a new design and may therefore require a proposed license submittal and technical specification change. It is not possible, however, to supply pertinent information on dates. As information concerning fuel design, core configuration, Operational Review Committee determinations, proposed licensing action, and Technical Specification submittals becomes available, it will be forwarded to you.
7. (a) There are 580 fuel assemblies in the core.

(b) There are 580 fuel assemblies in the spent fuel pool.

8. (a) The station is presently licensed to store 2320 spent fuel assemblies.

The actual spent fuel storage capacity is 1160 fuel assemblies and new high density fuel storage racks are in the process of being installed.

(b) The planned spent fuel storage capacity is 2320 fuel assemblies.

9. b'ith present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 580 fuel assemblies (one core).

366 135

PII.CRIf1 tillCI. EAR POWER STATIOri Month . June, 1979 MAlOR SAFETY REI.ATED MAINTENAtlCE CORRECTIVE ACTTON AS SOC TAT P.fi'~ '

SYSTE!! C0!!POtlErlT MAI.FUtlCT I O!1 calls E PIA l tit E? LANCE TO PREVENT RECURREf;CE 1.ER 1 "i n" Relief Valve I.eaking Pilot Valve Leakage Replace with Modified Topworks on Order None rel>u il t valve 29 'A' SSU Pump Bottom Bowl Worn Errosion and Corrosion Install New New Modified Assembly None Itowl Assemlil y 2 MOV-202-SA Possible deteriora- Exposure and Age Replaced Motors None None t1oV-202-5B tion of Teflon in-sulation on leads 29 Salt Service Corrosion Failure of Rubber Replaced '.in ing Inst alled flew Ruliber 1.Ined tion e

_U;8.Le r P [p i ng___ _ _ _ _ _ _ _ _

l.I n ing Pipe

") Salt Service Errosion of Seat 6 Replaced Seat fl/A None Wa t e r I.eaks filse And Dise Pump Disc Check Valve

-,%,.a--m -----w--. .m _ em- e-mmmmw- ee.=am--e. -Ne-w - = e-m-..mmm-+---mai.%-, -- w ._w-.- -- - - - , , ,

-% - -. . - - - --- m. em -w ew-*u m'- + 6 =- we--*--*-- mewe.--e-_-N--g m e-w. wee ----e me wwe--n_ m-s--e ON ON ON J