ML20003E154
| ML20003E154 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 02/28/1981 |
| From: | Gridley R, Hughes R GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20003E138 | List: |
| References | |
| 81NED252, NEDO-21363-S03, NEDO-21363-S3, NUDOCS 8104020352 | |
| Download: ML20003E154 (8) | |
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NED0-21363-3 Supplement 3 81NED252 Class I February i981 GENERAL ELECTRIC BOILING WATER REACTOR RELOAD 1 LICENSING AMENDMENT FOR PEACH BOTTOM ATOMIC POWER STATION UNIT NO. 3 FAST SCRAM CONTROL ROD DRIVE THIRD SUPPLEMENT Approved:
Approved:
R. L. 'Hugh, Manager R.
. Gridley Manager Reactor Equipment Design Fuel and Services Licensing Nuclear Power Systems Safety and Licensing Operation Engineering Department NUCLE AR POWER SYSTEMS DivlSION e GENERAL E LECTRIC COMPANY SAN JOSE. CALIFORNI A 95125
@3 040 2 0%P GENER AL h ELECTRIC
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NED0-21363-3 o
IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT (Please Read Carefully)
This report was prepared by General Electric solely for Philadelphia Electric Company (PECo) for PECo's use with the U.S. Nuclear Regulatory Commission (USNRC) for amending PECo's operating 14. cense of the Peach Bottom Atomic Power Station Unit 3.
The information contained in this report is believed by General Electric to be an accurate and true representation of the facts known, obtained or provided to General Electric at the time this report was prepared.
-The only_ undertakings of the General Electric Company respecting information in this document are contained in the Test Agreement between Philadelphia Electric Company and GeneraY Electric Company and nothin contained in this document.shall be construed as changing said contract. The use of this information except as defined by said contract, or for any purpose other than that for which it is intended, is not authorized; and with respect to any such unauthorized use, neither General Electric nor any of the contributors to this document.makes any representation or warranty (express or implied) as to the completeness, accuracy _or usefulness of the information contained in.this document or that such use of such information may not infringe privately owned rights; nor do they assume any responsibility for liability or damage of'any kind which may result from such use of such information.
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NEDO-21363-3 TABLE OF CONTENTS Page 1.
INTRODUCTION 1-1 2.
REPORT OF FINDINGS 2-1 3.
SAFETY EVALUATION 3-1 4.
REFERENCES 4-1 t
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NEDO-21363-3 1.
INTRODUCTION This third fast scram control rod drive (FSCRD) supplement to NED0-21363 (Reference 1) provides information to support the third cycle of reactor operation for the FSCRD (S/N 7464). NEDO-21363-2 (Reference 2) described the first FSCRD (S/N 7067) and supported its installation and operation in the Peach Bottom 3 reactor during cycle 2.
The first FSCRD was removed and inspected (Reference 3) at the end of Peach Bottom 3 cycle 2 and replaced by FSCRD (S/N 7464) which is presently in operation during cycle 4 (Reference. 4).
The purpose of this report is to provide the results of the performance data that is presently available. Along with the inspection results of FSCRD (S/N 7067) sannarized in Reference 3 and safety evaluation provided in ReferenceL2, it la demonstrated that continued operation of FSCRD (S/N 7464) during cycle 5 does not introduce an unreviewed safety question and has no effect on the parameters used in the Safety Analysis (Reference 5).
The intent of the FSCRD test program is to continue to utilize the FSCRD for several additional cycles to accumulate long-range experience in the reactor environment.
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NEDO-21363-3 2.
REPORT OF FINDINGS The first of two FSCRDs (S/N 7067) was subjected to one year (cycle 2) of continuous reactor operation before being replaced by the second FSCRD (S/N 7464). During this period, the drive performance was monitored.
The data showed no abnormality of drive functions (insert, withdraw, scram) during the cycle. Visual examination of the drive components at Peach Bottom 3 site in April 1978 revealed no unusual conditions. Reference 3 described the results of these examinations and summarized the drive activ-ities of-FSCRD S/N 7067.
A summary of recorded drive activities of FSCRD S/N 7464 is provided in Table 2-1.
A sample of scram time test data is provided in Table 2-2.
1he scram times exhibited by the FSCRDs are approximately the same as the average times of the present design.
It was noted in NEDO-21363-2 (Reference 2) that, although BWR/6 drive pressure (1200 psi) normally supplied by the BWR/6 Hydraulic Control Units (HCUs) could not be used in Peach Bottom 3, the N Precharge for FSCRD field 2
evaluation would be increased from ~575 psi at 70 F to ~769 psi at 70 F in order to obtain a predominantly " accumulator scram", rather than a " vessel scram".
The accumulator pressure was inadvertently reduced to the normal pressure (~575 psi)
-during the course of.some'of the tests; therefore, not all of the scram times reflect the increased accumulator pressure. For example, the longer initial scram time (0.330 sec) during the period of 9/8/78 to 11/15/78 is attributed to the inadvertent reduction of the accumulator pressure. The longer 90% scram time (04 PU) during the period of 5/21/79 to 8/31/79 is due to the lower reactor pressure (945 psi) at'the time of the scram event.
It should be noted that vessel pressure is required'to complete the scram stroke. Data show that the reactor pressure during scrams at other time periods ranged from 980 to 1000 psi.
Considering'the differences in accumulator pressure and reactor pressure, all of the scram times are in the expected' range.for the given conditions.
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NEDO-21363-3 Table 2-1
SUMMARY
OF RECORDED ACTIVITIES ( }
FOR FSCRD S/N 7464 Insert Withdrawal Scrams Number of Operations April 1978 to December 1980 80 250 62(2)
Table 2-2 SCRAM TIME TEST (ROD NO. 26-23) (FSCRD SN 7464)
(Pr er 1000 psi)
Measured Times and Data Tape Dates ( }
6/29/78 9/8/78 1/15/79 5/21/79 7/21/80 Position to to to to to Indicating 9/8/78 11/15/78 2/13/79 8/31/79 1 /3/80 Switch No.
(sec)
(sec)
(sec)
(sec)
(sec) 46 DO 0.270 0.330 0.290 0.280 0.250 38 PU 0.672 0.810 0.730 0.700 0.610 24 PU 1.470 1.610 1.500 1.620 1.260 04 PU 2.560(3) 2.730(3) 2.660 2.920 2.220(3)
From Automatic Data Gathering System (ADGS) Recordings.
These represent all scrams, including short stroke scrats, and scram tests.
Interpolated between position 08 and full-in.
DO = Drop Out PU = Pick Up 2-2
NEDO-21363-3 3.
SAFETY EVALUATION NED0-21363-2 (Reference 2) provided a safety evaluation of operation of Peach Bottom 3 with a FSCRD installed.
The evaluation considered the three requirements of 10CFR50.59 and concluded that no unreviewed safety question was introduced by the FSCRD. This safety evaluation is also applicable for operation of the currently installed FSCRD (S/N 7464) during cycle 5 operation.
The report on the performance of the first FSCRD (Reference 3), and the performance of the second FSCRD (S/N 7464) during its two cyclee of operation in Peach Bottom 3 (cycle 3 and cycle 4) demonstrates that the continued oper-ation of FSCRD S/N 7464 during cycle 5 will not introduce an unreviewed safety question.
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REFERENCES l
1.
General Electric Boiling Water Reactor Reload 1 Licensing Amendment for Peach Bottom Atomic Power Station Unit Number 3, November 1976 (NEDO-21363).
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- 2. ' General Electric Boiling Water Peactor Reload 1 Licensing Amendment for Peach Bottom Atomic Power Station Unit Number 3, Fast Scram Control
- Rod Drive Supplement, November 1976 (NEDO-21363-2).
3.
General Electric Boiling Water Reactor Reload 1 Licensing Amendment for Peach Bottom Atomic Power Station Unit No. 3 Fast Scram Control Rod Drive Second Supplement, July 1979 (NED0-21363-2A).
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4.
Supplemental Reload Licensing-Submittal for Peach Botton Atomic Power Station Unit.3, Reload 3, July 1979 (NEDO-24204A).
- 5. : Supplemental Reload L* censing Submittal for Peach Bottom Atomic Power Station Unit 3, Reload 4, February 1981 (Y1003J01A20).
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