ML19344D263

Rept of Startup Following Third Refueling Outage,Sept 1979.

ML19344D263
Person / Time
Site:	Peach Bottom
Issue date:	03/05/1980
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML19344D262	List: ML19344D261 ML19344D263
References
NUDOCS 8003110609
Download: ML19344D263 (6)

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I PHILADELPHIA ELECTRIC COMPANY j

. PHILADELPHIA PEACH BOTTOM ATOMIC POWER STATION UNIT NO. 3 DOCZET NUMBER 50-276 REPORT OF PLANT ST12r-UP FOLLCVING THIRD 102U1;1EG OUTAGE .

wider 1979

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SUBMITTED TO ,

TEE GTITED STATES NUOLEAR REGULATORY CCMCSSICN -

l PURSUA5T TO N FACILTFf OPERATING LICENSE NO. DPR-56 .

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8003110 dcdp-

PHILADELPHIA ELECTRIC COMPANY Peach Bottom Atomic Power Station Unit No.

Docket Number 50-278 .

REPORT OF PLANT START-UP FOLLOWING THIRD REFUELING OUTAGE e SEPTEMBER, 1979 SU3MITTED TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION PURSUANT TO FACILITY OPERATING LICENSEE DPR-56 Preparation Directed By:

W. T. Ullrich, Superintendent Peach B ot t om At omic P owe r S tation RD'#1 Delta, PA 17314 i

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J TABLE OF CONTENTS Page INTRODUCTION ............................................... 1

SUMMARY

OF TESTS L. Verification of Shutdown Margin ........................ 2

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

3. LPRM Calibration ....................................... 2

4. Reactivity Anomalies ................................... 2

5. Core Verification ...................................... 2

6. Cold' Critical Rod Pattern Prediction ................... 3

7. Core Power Symme try and TIP Reproducibility Test ................................................... 3

8. Control Rod Drive Scram Timing ......................... 3

9. RHR Redundant Start Logic Modification ................. 3 s

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INTRODUCTION The Peach Bottom Technical Specification 691 Routine Reports requires submittal of a startup report following any outage in 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, describes the startup program imp lemented t o p rovide assurance that the safe op era tion of -

the plant was not diminished by the activities of the third refueling outage.

The Peach Bottom Unit 3 was out of service from September 15, 1979, to N ove mb e r 5, 1979, to accommodate a maintenance /refu, ling outage.

During this 52 day outage, 271 fuel bu ndles of the original (717) design and one (8X8) were replaced with the new (dX8R?) fue.1 design.

The new fuel was manufactured by the General Electric Company and was designed t o p rovide additional operational flexibility and fuel economy. The unit was returned to service on November 5, 1979. and

. reached f ull power on November 15, 1979. S t a rt -up tests were .

performed before and during the return t o p ow e r .

The startup tests identified in the F.S.A.R. were addressed and those which involve areas whien were affected by outage activities were included and are summarized herein. Additional special tes ts connected with specific outage activities were als o included in the program and are discussed in this report. The successful imp le me n t a t i on of this startup program insures that the Unit 3 refueling outage has resulted in no conditions or system chaeacteristics that in any way diminish the s af e op e ra ti on of the Unit. .

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

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1. V I; d l. F. I C. A T I D.H O. r. $.11 U T_ D. O.W. tl ti.A.R G I!4.

The core shutdown margin was determined during the initial reactor criticality in the A-2 sequence. The actual shutdown margin was 1.63%

AK/ K . as compared with a Technical Specification minimum value ot 0.38% AK/ K. This test was performed on November 5, 1979.

2. . C.O N.T_ R_ O L. . R 0 DO. P.E._R_. A. B I. L_ I.T.Y. . A.i4 D .S.U S_C. R. I.T. I_ C. A_L I.T.Y. _C. ll. E.C.K.

Each control rod was withdrawn and inserted and suberiticality verified per surveillance test ST 10.8. The test was completed on November 4 1979, prior to start up.

3. . L. P.R.t1 . C_ A. L. .I. B. .R_ A._ T__ I_ O N LPRM calibrations were performed at approximately 25%, 50%, and 100%

power levels per surveillance test ST 3.4.1.

4. . R E A C_T_ I_V I T. Y A.N..O_ M. A L. I.. E. S. .

Surveillance test ST 3.7, " Reactivity Anomalies". was successfully performed un November 19, 1979. The predicted number of control rod notches inserted at ated conditions was 900 with a +, 1% AKeff range of 650 to 1150 contro; rod notches inserted. The actual number of control rod notches inserted was 736, which satisfies the + 1%21Keff criteria.

5. .- C.O R E. .V. E R I. F I. C A T. I_ O N

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The Unit 3 beginning ut core four (SOC 4) post alteration core

verification was performed on October 16, 1979 in accordance with r surveillance test ST 12.10 " Core-Post-Alteration Verification". Two l fuel bundles were in the wrong location and were moved to their proper l locations. A-reverification was performed for the corrective fuel l movement . A seating verification was performed for all fuel

, assemt is. Seve ral a ssemblies were improperly seated. These l assem as were reseated and reverified.

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6. COLD CRITICAL ROD PATTERN PREDICTION The cold critical rod pattern prediction c omp a ris on surveillance test ST 3.9 was successfully perf ormed f or Unit 3 The predicted core keff was 1.003 and the actual core keff was 1 011 for a difference of

-0 008. The difference is -0.8% and satisfies the 1 test acceptance criteria.

7. CORE POWER SYMMETRY AND TIP REPRODUCIBILITY TEST Core p ower symme t ry and TIP rep rodu cibili ty test data was analyzed f or sequence 'A' conditions on 12/6/79 (75: p ow e r ) . Two data sets were taken. The total TIP uncertainty was 2 95% and 3.2 7 % f or the two sets; therefore the test criteria that the total TIP uncertainty not to exceed 9: is satisfied. The maximum deviation between symmetrically located pairs was 16.2% and 15.6% for the two s ets .

which satisfies the 25% acceptance criteria.

8. CONTROL ROD DRIVE SCRAM _ TIM ING All 185 control rods were scram timed satisfactorily following all core alterations at nominal reactor p ressure of 1000 psig in accordance with surveillance test ST 10.7. Technical Specification requirements were all satisfied.

9 RHR REDUNDANT START LOGIC MODIFICATION A modification was completed on Unit 3 to revise the RHR pump start logic so that each pump receives a start signal f rom both A & B initiation logic.

The modification was tested satisfactorily using a logic system f unctional s urveillance test with additions to p rove proper op e ra ti on of the changes.