ML20080F980

Rept of Plant Startup Following Fifth Refueling Outage, Feb 1983.

ML20080F980
Person / Time
Site:	Peach Bottom
Issue date:	02/14/1983
From:	Fleischmann R PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8402130223
Download: ML20080F980 (5)

Text

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PHILADELPHIA ELECTRIC COMPAN _

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PHILADELPHIA

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PEACil BOTTOM ATOMIC POWER STATION

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.' UNIT NO. 3 .

, , DOCKET NUMBER 50-278 4

m REPORT OF' PLANT START-UP FOLLOWING

, FIFTH' REFUELING OUTAGE

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FEBRUARY 1983 '

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. SUBMITTED TO

/ I> THE UNITED' STATES NUCLEAR REGULATORY' COMMISSION

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FACILITY-OPERATING LICENSE NO. DPR-56 '

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I I PHILADELPHIA ELECTRIC COMPANY Peach Bottom Atomic Power Station Unit No. 3 Docket Number 50-278 I .

I REPORT OF PLANT START-UP FOLLOWING I FIFTH REFUELING OUTAGE FEBRUARY 14, 1983 I

SUBMITTED TO I THE UNITED STATED NUCLEAR REGULATORY COMMISSION PURSUANT TO FACILITY OPERATING LICENSEE DPR-56 I

Preparation Directed By:

R. S. Fleischmann, II Peach Bottom Atomic Power Station

'l RD #1 E Delta, PA 17314 t

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Docket No. 50-278 TABLE OF CONTENTS I

I INTRODUCTION................................................ 3 I .

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SUMMARY

OF TESTS I

I 1. Verification of Shutdown Margin......................... 4

2. Control Rod Operability and Subcriticality Check........ 4

3. LPRM Calibration........................................ 4

4. Benetivity Anomalies.................................... 4

5. Cor e v e r i f i ca t i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5

6. Cold Critical Rod Pattern Prediction.................... 5

7. Core Power Symmetry and TIP Reproducibility Test. . . . . . . . 5

8. Control Rod Drive Scram Timing.......................... 5

9. Recirculation and RHR Piping............................ 5 I

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LDocket No. 50-278 INTRODUCTION The Peach Bottom Technical Specification 6.9.1 Routine Reports requires submittal of a startup report following any outage in a which certain safety related events may occur. Installation of fuel of a different design is one of these events. This report, prepared to meet the Technical Specification requirement, I describes the startup program implemented to provide assurance that the safe operation of the plant was not diminished by the activities of the fifth refueling outage.

The Peach Bottom Unit 3 was out of service from February 13, 1983, to September 2, 1983, to accommodate a maintenance and refueling outage. During the 201 day outage, 23 bundles of the I (8x8) design, 252 (8x8R), and 9 (P 8x8 R) were replaced with 280 bundles of the (P 8x8 R) fuel design and 4 Lead Test Assembly (LTA). The unit was returned to service on September 2, 1983, I and reached full power on November 3, 1983. Start-up tests were performed before and during the return to power.

The startup tests identified in the F.S.A.R. were addressed and those which involve areas which were affected by outage activities were included and are summarized herein. Additional special tests connected with specific outage activities were also I included in the program and are discussed in this report. The successful implementation of this startup program insures that the Unit 3 refueling outage has resulted in no conditions or system characteristics that in any way diminish the safe I operation of the Unit.

The tests and data referenced in this report are on file at the Peach Bottom Atomic Power Station.

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Docket No. 50-278 STARTUP REPORT '

Peach Bottom Atomic Power Station ..

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UNIT NO. 3 ['

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1. 'VEPIFICATION OF SHUTDOWN MARGIN -

5 An 'in-sequence' SDM determination was performed during the ~,

initial reactor startup in the A sequence. The actual t shutdown margin was l~.741 delta K/K, as compared with a

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c I Technical Specification minimum value of 0.38% +R delta K/K, where R, for this cycle, is 0.0. This test was performed on September 3, 1983.

2. CONTROL ROD OPERABILITY AND SUBCRITICALITY CHECK  ; {

I Each control rod was withdrawn and inserted. Subcriticality was verified per surveillance test ST 10.8. The test was -

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completed on September 1, 1983, prior to start-up. ,

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3. LPRM CALIBRATION ,

LPRM calibrations were successfully performed at approximately 35% Rated Thermal Power (RCTP), on October 16, 1983, and 89% RCTP, on October 26, 1983, in accordance with  !

surveillance test ST 3.4.1. _

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4. REACTIVITY ANOMALIES I Surveillance test ST 3.7, " Reactivity Anomalies", was .1 -

successfully performed on October 31, 1983. The predicted -D '

number of control rod notches inserted at rated conditions I was 750 with a + 1% delta Keff range of 390 to 1090 control =

rod notches inserted. The actual number of control rod - '

notches inserted was 613, which satisfies the + 1% delta Keff -

I criteria.

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I Docket No. 50-278

5. CORE VERIFICATION Post alteration core verification (bundle location, seating,

. orientation) was completed on June 22, 1983, in accordance O with surveillance test ST 12.10, " Core Post-Alteration Verification." All fuel bundles were verified to be j' correctly located, seated, and oriented prior to cycle 6 5 startup and operation.

6. COLD CRITICAL ROD PATTERN PREDICTION The cold critical rod pattern prediction comparison I surveillance test ST 3.9 was successfully performed for Unit

3. The predicted core Keff was 1.0017 and the actual core Keff was 1.0058 for a difference of -0.0041. The difference is -0.41% and satisfies the + 1% test acceptance cirteria.

7. CORE POWER SYMMETRY AND TIP REPRODUCIBILITY TEST 5 The core power symmetry and TIP reproducibility test data was analyzed for sequence A' conditions on November 9, 1983, at rated power. The total TIP uncertainty was 3.72%; therefore, I the test criteria that the total TIP uncertainty not exceed 8.7% is satisfied. The maximum deviation between symmetrically located pairs (LPRM strings 9 and 21) was 13.7%, which satisfies the 25% acceptance criteria.

8. CONTROL ROD DRIVE SCRAM TIMING The control rod scram time surveillance test ST 10.7 was I completed satisfactorily on June 22, 1983, for all 185 control rods. The nominal reactor pressure, during the test, was approximately 900 psig. The test results satisfied all Technical Specification requirements.

9. RECIRCULATION AND RHR PIPING Inspections and repairs for IGSCC were performed in accordance with Bulletin 83-02. Separate reports were submitted to the NRC (dated August 9, 1983, August 22, 1983, and August 30, 1983) prior to startup for NRC concurrence.

I On Se:ptember 1, 1983, the NRC issued Confirmatory Orders which authorized plant restart.

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• PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 12151841 4000 January 31, 1984 Docket No. 50-278 Dr. Thomas E. Murley -

Of fico of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 SUBJECP : Report of Plant Startup Following Fif th Refueling Outage, February 1983 Peach Bottom Atomic Power Station, Unit #3 Docket No. 50-278

Dear Dr._ Murley:

Enclosed are two copies of the Plant Startup Following the Fifth Refueling Outage Report for Peach Bottom Atomic Power

' S tatial Unit No. 3 - February, 1983.

This report is being submitted in compliance with the Technical Specifications- for Operating License DPR-56.

Very truly yours,

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Engi ne er-In-Char ge Licening Section Nuclear Generation Division MBR: vdw cc: A. R. Blough, Site Inepector

' Director, Of fice of Inspection & Enforcement, NRC l