ML20125A802
| ML20125A802 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/31/1979 |
| From: | Beatty G FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20125A800 | List: |
| References | |
| 3--1-C2, 3-0-1-C2, NUDOCS 7908170413 | |
| Download: ML20125A802 (6) | |
Text
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FLORCA POWER CORP 2RATl!N JNTERDFFICI CORRESPONDENCE CRYSTAT RTVER UMTT 3 (Office - Location) subject: NRC Monthly Operating Report Date: July 31, 1979 3-0-1-C2 Attention Of:
T: Patsy,Baynard Attached is the Crystal River Unit #3 JUI V. 1979 input to the NRC Monthly Operating Report required by Regulatory Guide 1.16.
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p,r[GuyBeatty,Jr.
uclear Plant Superintendent CC:
A.E. Friend E.C. Simpson 7
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I DOCKET NO. _50-302 UNIT SilUTDOWNS AND PO17ER REDUCTIONS UNIT NAME FLCRP-3 8/2/79 DATE W. A. Stephenson COMPLETED BY REPORT MONTII JULY. 1979 TELEPilONE (904)795-6486 "E
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Cause & Corrective licensee
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Action to No.
Date g
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~59 Repost #
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!O Preunt Recurrence g$ 5 5
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79-11 790423 S
743 C
1 ZZ ZZZZZZ Shutdown 790423 for refueling.
Refueling. completed in June; however, outage was extended for inspection under I. E.Bulletin 79-02 and repair to reactor coolant pump seals.
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2 Methm!:
Exhibit G -Instructions F: Forced Reason:
for Preparation of Data 1-Manual a
S: Scheduled A-Equipment Failure (Explain)
Entry Sheets for Licensee B-Maintenance of Test 2-Manual Scram.
3-Automatic Scram-Event ReporI(LER) File (NUREG-C-Refueling 44)ther (Explain) 0161)
D-Regulatory Restriction E-Operator Training & Ucense Examination 5
F-Administrative Exhibit I-Same Source G-Operational Error (Explain) 19/7 7) li Other (Explain)
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t AVERAGE DAILY UNIT POWER LEVEL DOCKETNO. 50-302 UNIT W RP-3 DATE 8/2/79 COMPLETED BY W. A. Stephenson TELEPilONE (904)795-6486 MONTH JULY. 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe. Net) 0 I
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0 18 0
3 0
39 0
4 0
20 0
5 0
21 0
0 6
0 2'2 7
0 23 n
~
8 0
24 0
9 0
25 0
10 0
26 0
11 0
27 0
12 0
28 0
13 0
29 0
14 0
30 0
15 0
3 o
16 0
INSTRUCTIONS On this format, list the average daily unit power level in MWe. Net for each day in the reporting month. Compute io the nearest whole megawatt.
(9/77)
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4 OPERATING DATA REPORT DOCKET NO.s 50-302 DATE:
C/2/79 COMPLETED DY: W.A.STEPHENSON TELEPHONE:(904) 795-6406 PLCHC129 LT21.L5 1
I IN0TES I
DHIT NAME-CFYSTAL RIVER N3 l
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. REPORTING PERIOD: 7/1/79 + 7/31/79 l
l LICENSED THERMAL POWER (HWT):
2452 I
I NAMEPLATE RATING (GROSS MWE):
890 l
l DESIGN ELECTRICAL RATING (NET MWE);
825 l
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MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):
835 1
i MALInUM DEPENDABLE CAPACITY (NET MWE):
797 i
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IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 1) SINCE LAST REPORT GIVE REASONGr......
__.....................___.J.
POWER LEVEL TO WHICH RESTRICTED.IF ANY(NET MWE): NONE REASONS FOR RESTRICTIONS, IF ANY:.___....__.........____._
.........=
THIS MONTH YR.-TO-DATE CUMULATIVE 5087 20903
- 11. HOURS IN REPORTING PERIOD 744
- 12. NUMBER Or HOURS REACTOR WAS CRITICAL 54.2 2336.7 12193.9
- 23. REACTOR RESEkVE SHUTDOWN HOURS 496.1 729.5 1102.9
- 14. HOURS GENERATOR ON-LINE 1.0 2255.6 11800.2 15 UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 16. GROSS THERMAL ENEPGY GENERATED (MWH) 2587 5005075 25602243
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 137 1707507 8705352
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 0 1615921 8245786 19.< UNIT SERVICE FACTOR
.1e/*
44.3=/*
56.5+/*
- 20. UNIT AVAILABILITY FACTOR
.1./.
44.3./*
56.5a/+
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0*/*.
o 39.9+/+
49.5=/*
- 22. UNIT CAFACITY FACTOR (USING DER NET) 0.0+/*
38.5+/+
47.8 /.
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- 23. UNIT FORCED OUTAGE RATE 99.9./*
33.3+/*
36.5./=
- 24. SHUTDOWNS SCHEDULED DVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)*
- 25. IF' SHUT DOWM AT END OF REPORT PERIOD, ESTIMATED I' ATE OF STARTUP-
- 26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):
FORECAST ACHIEVED INITIAL CRITICALITY 1/14/77
- !NI/IAL ELECTRICITY 1/30/77 COMMERCIAL OPERATION 3/13/77 l
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(Continued) b.
Filed request on January'9, 1978 with NRC concerning expansion of Pool A from 120 to 544 assemblies plus 6 failed fuel assem-blies and expansion of Pool B from 120 to 609 assemblies.
Ex-pansion of Pool A is to occur.at the refueling in April,1980.
The Pool B expansion will occur at a later refueling outage (approximately1986).
Additional detailed design information concerning our fuel pool expansion was submitted to the Commission on March 3, March 22,1978, January 18,1979, March 16,1979, and June 29, 1979.
9.
The projected date of the last refuelin9 that can be discharged to {he spent fuel assuming the present licensed capacity.
1981-1982.
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M0flTHL STATUS REP 0,RT REFUELING IflFORMATION RLQUEST 1.
Name of Facility:
Crystal River Unit 3 i
2.
Scheduled date of next refueling shutdown: April, 1980.
3.
Scheduled date for restart following refueling:
June, 1980.
'4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes.
In general, changes to the CR #3 technical specifications will include:
-a.
Moderator Temperature Coefficient (3.1.1.3) b.
Control Rod Insertion Limits (3.1.3.6) c.
Control Rod Group Assignments (3.1.3.7) d.
Axial Imbalance Limits (3.2.1) e.
Refueling Boron Concentration (3.9.1)
These specifications will be reviewed and changed as necessary based on the reactivity of the second cycle as compared to that of the first cycle.
5.
Scheduled date(s) for subnitting proposed licensing action and supporting information:
February, 1980.
6.
Important licensing considerations associated with refueling, e.g.,
new or different fuel design or supplier, unreviewed design or perfor-mance analysis methods, significant chan,g.es in fuel design, or new opera-ting procedures.
Florida Power Corporation is presently discussing with the flRC staff our intent to request that the power level of CR #3 be ' raised f rom the present level of 2452 MW (t) to the ultimate core power level of 2544 MW (t) as described in the CR #3 FSAR.
FPC submitted on february 28. I'll'1 our reload report justifying Cycle 2 operation of CR #3 at 2544 MW (t).
On May 25, 1979, FPC modified its Cycle 2 reload report justifying continued operation at 2452.MW (t).
It is our intent to continue our discussions with the NRC in order to obtain the power upgrade at a later date.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
a) 177 assemblies b) 60 assemblies 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storaae capacity that has been requested or is planned, in number of fuel assemblies.
a.
Present storage capacity - Pool A - 120 plus 8 failed fuel assemblies Pool B - 120 plus 8 failed fuel assembifes e