ML20137W822

From kanterella
Jump to navigation Jump to search
Annual Operating Rept for Jan-Dec 1996, Including Personnel & man-rem Exposure by Work & Job Function
ML20137W822
Person / Time
Site: Cooper Entergy icon.png
Issue date: 12/31/1996
From: Graham P
NEBRASKA PUBLIC POWER DISTRICT
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLS970059, NUDOCS 9704210012
Download: ML20137W822 (10)


Text

.-

h P.O. BOX B L NEB 68M1

$. x Nebraska Public Power District "ME""

w , _ _ . _ - . . _ - - . - - _ . - -

NLS970059 April 14,1997 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

Subject:

Annual Operating Report Cooper Nuclear Station NRC Docket No. 50-298, DPR-46 Gentlemen:

In accordance with Paragraph 6.5.1.C of the Cooper Nuclear Station Technical Specifications, the Nebraska Public Power District hereby submits the Cooper Nuclear Station Annual Operating Report for the period of January 1,1996, through December 31,1996.

We are enclosing one signed original for your use, and in accordance with 10 CFR 50.4, are transmitting one copy to the NRC Regional Office, and one copy to the NRC Resident Inspector for Cooper Nuclear Station.

Should you have any questions or comments regarding this report, please contact me.

Sincerely, PB&L P. D. Graham Vice President of Nuclear Energy Cooper Nuclear Station PDG:lb 9704210012 961231 PDR ADOCK 05000298 Attachment R PDR cc: NRC Regional Office I Region IV Arlington, Texas

'[1 l NRC Resident Inspector Cooper Nuclear Station 180051 REIRS Project Manager (w/ Personnel Man-Rem Report only)

Office of NRR - USNRC llHilllallHpll1,ll!lllll!HE Washington, DC hkW

=m _e:

? k l W N W N$$((?$l1blANI?$$$YYnVU S S W em == ==================

01 F$M

==== === ==ee

%bN

l I

U.S. Nuclear Regulatory Commission April 14,1997 Page 2 Plant Manager Cooper Nuclear Station NPG Distribution l

l

4 4

I .

l a

j COOPER NUCLEAR STATION BROWNVILLE, NEBRASKA l

ANNUAL OPERATING REPORT JANUARY 1,1996, TIIROUGII DECEMBER 31,1996 USNRC DOCKET 50-?.98 f-

['-

TABLE OF CONTENTS i

I SECTION PAGE

1. PERFORM ANCE CH ARACTERISTICS . . . . . . . . . . . . . . . . . . . . 1 i Fuel Perfonnance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 j MSV and MSRV Failures and Challenges . . . . . .......... ....... 3 II. PERSONNEL AND MAN-REM EXPOSURE . . . . . . . . . . . . . . . . . . 4 By Work and Job Function . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5

\

4 a

i i

4 4

i 1

l i

I l

li

9 8 l

e 1 I

1 l

l 1

l 1

1

1. PERFORMANCE CIIARACTERISTICS i

i i

1 l

l l

{

? l 1

I I l l 1

l

FUEL PERFORMANCE Normal full power operation was maintained during January, February, and March 1996. On March 30,1996, increases in off gas activities indicated a potential leak in the fuel. Activity levels increased again on March 31,1996, indicating a fuel failure had occurred in the core. Reduced power operation was implemented later that week. Activity levels indicated only one or two fuel pins were leaking. Power suppression testing was implemented to detect the location of the fuel leak in the core and to quantify the number ofleaking fuel pins. Suppression testing identified the location of the fuel leak and flux suppression techniques were imple nented to reduce power in the leak location. A siow power ramp was implemented and full power operation resumed. Activity levels continued to increase and trends identified that power limitations would be required later in the cycle. A shutdown and replacement of the leaking fuel were directed by plant management on June 1,1996. Sipping of the core identified one fuel bundle leaker. Tids fuel bundle and symmetric bundles were replaced in the core and the core shuffled to optimize the remaining cycle operation.

The plant returned to operation on June 10,1996 with no indication of further fuel leaks.

The remainder of Cycle 17 off gas activities continued at elevated levels due to the memory effect of the prior fuel leak. Reactor coolant dose equivalent I-131 and off gas release rates are well within the limits specified by the CNS Technical Specifications.

Comparisons of actual control rod densities predicted for the cycle against actual cycle operation at various core exposures indicate reactivity anomalies ofless than 1%.

1 l

I 2

- . ~. .. - .-- .. - . - - . . - . . ,

1 .

MSV AND MSRV FAILURES AND CHALLENGES

-(Ref.: NUREG-0737, Action Item II.k.3.3)

  • ' During 1996, the Safety Valves and Safety Relief Valves performed as expected. No leakage was noted during 1996. The Safety Valves and Safety Relief Valves were not required to operate in the automatic mode. The Safety Relief Valves were not required to operate in the manual mode. No surveillance testing that operated the valves was performed during 1996.

i I

i i

l i

l 1

i 1

l i

3 i

q 1

4 I

i I

i 1

l l

1 l

l l

l i

1

'; PERSONNEL AND MAN-REM EXPOSURE i

I l

l l

4

NEBRASKA PUBLIC POWER O! STRICT AENUAL REPORT Year af 1996 NUMBER OF PERSONNEL AND MAN REN BY WORK AND JOS FUNCTION l l Att Personnet ll Totet Man Rom l l l Stetton l Utility l Contractors ll Station l Utility l contractors l l Work & Job Function l Emptovees l Emptovees I and others ll E stovees l E etovees I and others l REACTOR OPERATION & SURVEIL MAINTENANCE 1 04 6 21 2.392 0.010 1.224 OPERATIONS PERSONNEL 83 0 0 7.581 0.000 0.000

-NEALTH FHYSICS 49 1 12 4.341 0.000 0.381

-SUPERVISORY PERSONNEL 100 7 145 0.823 0.007 0.624

-ENGINEERING PERSONNEL 128 4 171 1.734 0.005 2.105 ROUTINE MAINTENANCE MAINTENANCE 128 2 22 8.359 0.000 1.261 OPERATIONS PERSONNFL 63 0 0 3.307 0.000 0.000

  • NEALTH PHYSICS 40 0 17 4.731 0.000 0.652

-SUPERVISORY PERSONNEL 56 2 3 0.557 0.002 0.000 ENGINEER!kG PERSONNEL 68 2 63 0.412 0.005 0.655

!NSERVICE INSPECTION

-MAINTENANCE 0 0 0 0.000 0.000 0.000 0PERATIONS PERSONNEL 0 0 0 0.000 0.000 0.000

-HEALTH PHYSICS 0 0 0 0.000 0.000 0.000 SUPERVISORY PERSONNEL 0 0 0 0.000 0.000 0.000 EhGINEERING PERSONNEL 1 0 4 0.006 0.000 0.071 SPECIAL MAINTENANCE MAINTENANCE 82 1 10 5.002 0.002 0.584 OPERATIONS PERSONNEL 25 0 0 0.568 0.000 0.000

-HEALTH PHYSICS 31 0 9 1.944 0.000 1.189 SUPERVISORY PERSONNEL 18 2 3 0.549 0.001 0.007

-ENGINEERING PERSONNEL 37 0 30 0.590 0.000 1.631 WASTE PROCES$1NG MAINTENANCE 14 2 1 0.023 0.000 0.000

+0PERATIONS PERSONNEL 20 0 0 0.210 0.000 0.000

-NEALTH PHYSICS 19 0 6 0.891 0.000 1.621 SUPERVISORY PERSONNEL 2 2 0 0.069 0.000 0.000 ENGINEERING PERSONNEL 0 0 6 0.000 0.000 0.002 REFUELING MAINTENANCE 8 0 0 0.003 0.000 0.000

-OPERATIONS PERSONNEL 9 0 0 0.018 0.000 0.000 HEALTH PHYSICS 6 0 3 0.031 0.000 0.014 SUPERVISORY PERSONNEL 1 0 0 0.001 0.000 0.000 ENGINEERING PERSONNEL 2 0 5 0.006 0.000 0.070 TOTALS MAINTENANCE 336 11 54 15.778 0.012 3.069

-OPERATIONS PERSONNEL 200 0 0 11.684 0.000 0.000 HEALTH PHYSICS 145 1 47 11.939 0.000 3.856

-SUPERVISORY PERSONNEL 177 13 151 2.000 0.010 0.631 ENGINEERING PERSONNEL 236 6 279 2.748 0.010 4.534 sessce = = = =s s = = = = = = = = = = = = = = = = .. ... ... e s s a s s s = = = = . . a s . . .. . ..a z e s s s s s s s = = = = = s e s = = = = = = = = = = = = = = s s = = = = = = = = = s s = = = = = = = = = = = = = = = = =

GRAND TOTALS 1094 31 531 44.149 0.033 12.089 (s== =r= = === == == == ........... ========= =sses s ss s a s se s = = == ===== .....a s s = == ss e s s a s s n e s ..... es s s = = = = .. .s = == = = == = r 3 ==== = =

5

n-l ATTACHMENT 3 LIST OF NRC COMMITMENTS l Correspondence No: NLS970058 d

The following table identifies those actions committed to by the District in this document. Any other actions discussed in the submittal represent intended or planned actions by the District. They are described to the NRC for the NRC's information and are not regulatory commitments. Please notify the Licensing Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.

COMMITTED DATE COMMITMENT OR OUTAGE None l

l PROCEDURE NUMBER 0.42 l REVISION NUMBER 4 l PAGE 8 OF 9 l l