B16736, Monthly Operating Rept for Aug 1997 for Mnps,Unit 2
| ML20216H937 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/31/1997 |
| From: | Price J, Stark S NORTHEAST NUCLEAR ENERGY CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| B16736, NUDOCS 9709170114 | |
| Download: ML20216H937 (7) | |
Text
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Nuclear Energy Maieion. Nucie., ro.e, si.uon Northem Nu< lear Diegy Corupany l' 0. ikis 128 Waterhud, CT No85-0128 (2(0) 447 1791 l'as (2(0) 444 4277 n, Northe vuuue. sy.icm SEP 9 1997 Docket No. 50-336 B16736 Re: 10CFR50.71(a)
U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit No. 2 Facility Operating License No DPR-65 Monthly Operatino Report in accordance with the reporting requirements of Technical Specification Section 6.9.1.7 for Millstone Unit No. 2, enclosed, in Attachment 1, is the monthly operating report for the month of August 1997.
Veiy truly yours, NORTHEAST NUCLEAR ENERGY COMPANY t
g j
J. A. Prip Director, Millstone Unit No. 2
. cc:
H. J. Miller, Region i Administrator D. G. Mcdonald, Jr., NRC Senior Project Manager, Millstone Unit No. 2 D. P. Beaulieu, Senior Resident inspector, Millstone Unit No. 2 W. D. Travers, PhD, Director, Special Projects Office 9709170114 970831 PDR ADOCK 05000330 ll llllll lllll R
PDR th3422 8 REY.194
Docket No 50-336 B16736 4
Millstone Nuc%ar Power Station. Unit No. 2 Facility Operating License No. DPR-65 Monthly Operating Report September 1997
U.S. Nucle:r Regulatory Commission 816736%ttachment 1\\Page 1 DOCKET NO.:
$0-336 UNIT:
Millstone Unit 2 DATE:
9/2/97 COMPLETED llY:
S Stark TELEPilONE:
(860) 447 1791 EXT:
4419 MONTH: AUGUST 1997 DAY AVG. DAILY POWER LEVEL O 'sY AVO. DAILY POWER LEVEL (MWe Net)
(MWe Net) 1 0
17 0
2 0
18 0
3 0
19 0
4 0
20 0
5 0
21 0
0 0
22 0
7 0
23 0
8 0
24 0
0 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
31 0
16 0
INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month, Computed to the nearest whole megawatt.
,U.S. Nucle:r Regul: tory Commission B16736%ttachment 1\\Page 2 UNIT NAME Millstone Unit 2 DATC 09/02/97 COMPLETED BY S Stark TELEPHONE (860)447 1791 EXT 4419 i
OPERATING STATUS
- 1. Docket Number 50-336 2.
Reporting Period August Notes: Items 22 and 23 1997
- 3. Utikty Contact S. Stark cumulative are weighted 4 Licensed Thermal Power (MWt):
2700 averages. Unit operated at
- 5. Nameplate Rating (Gross MWe) 909 2500 MWTH prior to its 6.
Design Electrical Rating (Net MWe)'
870 uprating to its current 7 Maximum Dependable Capacity (Gross MWe) 901 63 2700 MWTH power level.
- 8. Maximum Dependable Capacity (Net MWe):
870 63
- 9. If Changes Occur in Capacity Ratings (Items Number 4 Throu0h 8) Since Last Report, Give Reasons N/A
- 10. Power Level To Which Restncted, if any (Net MWe)'
O
- 11. Reasons For Restrictions,if Any.
NRC Category ill Facahty; NRC Confirmatory Order requiring implementation of an independent corrective action verification program. NRC order requiring a third-party review of the employee concerns program at Millstone 2; design basis venfication response pursuant to 10CFR50 54(f)
This Yr..To-Date Cumulative Month
- 12. Hours in Reporting Penod 744 0 5831.0 190079 0
- 13. Number Of Hours Reactor Was Cntical 00 0.0 121911.7 14, Reactor Reserve Shutdown Hours 0.0 0.0 2205.5 15 Hours Generator On-Line 00 00 116611.9
- 16. Unit Reserve Shutdown Hours 0.0 00 468 2
- 17. Gross Thermal Energy Generated (MWH) 00 00 300862506 4
- 18. Gross Electncal Energy Generated (MWH) 0.0 00 98709460.0
- 19. Net Electrical Energy Generated (MWH) 1735 6 16218 2 94626694 2 20 Unit Service Factor 00 0.0 61.3
- 21. Unit Availabikty Factor 00 0.0 61.6
- 22. Unit Capacity Factor (Using MDC Net) 00
-0.0 58 1 23 Unit Capacity Factor (Using DER Net) 00 0.0 57.3
- 24. Unit Forced Outage Rate 100 0 100 0 22.4
- 25. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each)
Shutdown at the time of this report
- 26. If Unit Shutdown At End Of Report Penod, Estimated Date of Startup:
To be determined
- 27. Units in Test Status (Pnor to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A
U.S. Nuclear Regulatory Commisson B16736%ttachment 1Page 3 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:
50-336 UNIT NAME: Minstone Urnt 2 DATE' 09/02/97 COMPLETED BY.
S Sta-k TELEPHONE:
(8501447-1791 EXT; 4419 REPORT MONTH. Auoust 1997 No Date Type' Duratton Reason
- Method of License System Component Cause & Correcbve (Hours)
Shutung Event Code
- Code' Acton to Down Reactor' Report #
Prevent Recurrence l
97-01 03/07/96 S/F 744 B/D 4
N/A N/A N/A Scheduled _ Contmued med cycle survetitance testing from previous month Forced. Conbnued from previous month.. NRC Category ill fachty; NRC Con *rrmatory Order regurnng independent correcbve I
acbon verificat on. NRC order regurring third party review of Minstone Staten employee Cern.w., program.
design basis venficaten for response to NRC pursuant to 10CRF50.54(f)
F. Forced Reason
'Meth<x:
'tEEE Standard 805-1984 2
S: Scheduled A - Equipment Failure (Explam) 1 - Mr.nual hv.iu.,w.ded Pracbees B - Mamtenance or Test 2 - Manual Scram for System identficaten in C - Refueieng 3 - Automate Scram Nudear Power Plants and D - Regulatory Restnchon 4 - Contmued frem Previous Month Related Faolrbes-E - Operator Traming & License Examinaten 5 - Power Reducten (Duraten = 0)
F-Administratrve 6 - Other (Expiarn)
'IEEE Standard 803A-1983 hv.i...,s.ded Practrees G -Operatonal Error (Explam)
H - Other (Expla' )
for Uruque idedJa.dani in m
Power Plats and Related Fachte - CO. w, e-t Funcien identles-
_m__.__.-,-_
U.S. Nucle:r Regul: tory Commission
/
B16736%ttachment 1\\P;ge 4 4
BEFUELING INFORMATION REQUEST 1.
Name of the facility: Millstone Unit 2 2.
Scheduled date for next refueling outage: First Quarter of 1999 3.
Scheduled date for restart following refueling: Last Quarter of 1997 (Noto -
The current shutdown is not a refuelina outaae. This date represents the expected startuD date from the current shutdown )
4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes.
There are 12 Technica1 Specification Chance Reaqq11.3_OR license amendments which will be submitted to the NRC orior to startuo. These include the followina: 1)
Modify the minimum Instrument accurpcv for Meteoroloalcal Tower instrumentation. 2)
Eliminate the reference to the measurement location for the ultimate heat sink. 3)
Eliminate the reauirement to enter LCO 3.0.3 when the enclosure buildina is breached.
due to makina both trains of enclosure buildina ventilation system inoperable (unable tg create a vacuum within sDecified time period). 4) Redefine containment intearity to permit gDerator action durina Deriods when containment isolation valves may be opened under administrative controls. Also relocates the Ilst of containment isglation valves froJD Technical Specifications to Technical Reauirements Manual. 5) Modify the FSAR text tg resolve the emeraency diesel aenerator fuel oil storace capacity issues. 6) Revise several surveillance reauirements reaardina Control Room Ventilation System. 71 Certain RPS and ESAS trips did not consider the uncer1ainty associated with a Harsh Environment. Some RPS and ESAS setooints were based on 24 months instead of 18 months. 8) Verbatim compliance issues. ECCS throttle valves AFW surv. 9) Correct RCS Pressure / Temperature _gurves due to errors 10) Modify Table 3.71 to correct errors.
Beactor trio setooints for steam aenerator safety valves in Table 3.7-1 are incorrectiv based on 107% nower instead of 106.6%. ii) Reduce maximum containment pressure from 2.1 osia to 1.0 psia to suoDort accident analysis assumptions 12) Steam Generatol Blowdown monitorina instrumentation.
5, Scheduled date(s) for submitting licensing action and supporting information:
September 30.1997 6.
Important licensing considerations associated with refueling, e g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
Small Break LOCA analysis channes and Larae Break LOCA analysis chanaes.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
in Core: (a)
.Q,.
In Spent Fuel Pool: (b) 1QB1
- NOTE:
These numbers represent the total Fuel Assemblies and Consolidated Fuel Storace Boxes (3 total containina the fuel rods from 6 fuel assemblies) in these two (2) Item Control Areas.
s
U.S. Nucle _r Regul; tory Commission B18736%techm:nt 1\\P ga 5
,. 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 number of fuel assemblies:
Present storace capacity: 1306 storace locations 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming present license capacity:
_2001. Soenthelhel Full. Core offlqad capacity is reached 2005. Core Full. Spent Fuel Pool Full.
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