ML19350E541
| ML19350E541 | |
| Person / Time | |
|---|---|
| Site: | San Onofre, Arkansas Nuclear  |
| Issue date: | 04/10/1981 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| Shared Package | |
| ML19350E542 | List: |
| References | |
| ACRS-1831, NUDOCS 8106230254 | |
| Download: ML19350E541 (14) | |
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.'In ACRS SUBCOMMITTEE MEETING ON ELECTRICAL SYSTEMS' k
4 //OM MINUTES OF THE E
February 24 3 25, 1980
'J 1717 H ST., NW, WASHINGTON, DC
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The ACRS Subconmittee on Electrical ' Systems held a meeting on Feb'ruary 23 and. 24,.'
g, 1981 in Room 1046, 1717 H St., NW, Washington, DC.
Tnepurposeofthele'erfnI was to review matters relating to the ute of computer protection systems and the Combustion Engineering core protection calculator in the Arkansas Nuclear One, Unit 2 an.! San Oncfre, Units 2 a 3 plants.
An additional pu. pose was to discuss the Canadian ar.d U.S. experience with the use of computer protecti;n The systems and r.egulatory prac.tice applied to reactor control systems.
meeting was open to the public on' February 24, 1981.
The February 25, 1981 meeting was closed to the publ'c. The Designated Federal Employee for this meeting was Dr. Richard Savio.
Notice of this meeting appeared in the Federal Register, Volume 46, No. 29 on Fecruary 12, 1981.
A list of att.endees is.
Selected handouts for this meeting are iacluded as Enclosure 2.
A ccmplete set of handouts is in the ACRS Office Files.
EXECUTIVE SESSION (OPEN)
Dr. Kerr remarked that the meeting was being held in accordance with the Federal Advisory Committee act and the Government in the Sunshine Act.
He noted that no written comments had been received and that no requests for oral statements had been received.
Mr. Kerr noted in his opening remarks that the purpose of the meeting was to review matters relating to the use of computer protection systems and the Combustion Engineering core protection calculat ar.
He-noted that the results of this review would be utilized in the Committee's review of thc San Onofre Nuclear Reactor.
THIS DOCUMENT CONTAINS i P00R QUAUTY PAGES 8106 23 0 Q 6L T
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< ELECTRICAL. SYSTEMS 2 '-
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FEBRUARY 24 & 25. 1981'
, GENERAL SESSION Mr.'E. Kennedy, Combustion Engineering, stated that the discussion would cover computer' based reactor protection _ systems. in general and specif-feally, the Core. Calculator.
He said the Core Calculator is currently used at Arkansas Nuclear.One, Unit 2 (ANO-2), and will be used at San
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10nofre Units 2 and 3.
He noted that latsr speakers will compare the use.
of the core calculator at-ANO-2 and the future use at San Onafra 2 6 3, the differences between the two ~ systems, and the scftware changes which have been made since the Committee's A"0-2 OL retiew.
Mr. A. Spinnell." Combustion Engineering, stated that the presentation to follow would aodress the following subjects:
A.
Relatier.sbip of Core Protect's Calculator (CPC) trip anc the.
. remainder of plant protective systemt.
B.
Test and qualification of Arkansas Nuclear One, Unit-E' and San Onofre plant design (Core Protection Calculator System).
C.
Assessment of CPCS design after one and.one half years of operation at Arkansas Nuclear One, Unit 2.
'D.
The software modifications performed since the issuance of the ANC-2.0L and the relationship to the ANO-2 experience.
E.
The progress of testing and qualification of the San Onofre software.
A sthematic of the CPC3 is given on page 1 of Enclosure 2.
The CPCS design
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basis events and backup trip functions are summarized on pages 2 and' 3 of
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The existence of these backup trips form the basis for not censidering failure of the CPC as a design basis accident.
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' ELECTRICAL SYSTEMS' 3 '-
-a FEBRUARY =24 & 25, 1981 GENERAL SESSION (CONT'D)
Mri T. Cogburn-Arkansas Power and Light Company, discussed the ANO-2 experience.
He discussed the milestones an achieving commercial operation. He mentioned the itesting:of'the _CPC both prior to initial criticality and during power ascension
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(See pages 3-5 of-Enclosure'2).
He discussed "non-valid" CPC initiated trips and indi:ated that the number per-unit time _is_ decreasing, indicating. improve-a; ments in the system.'
The plant has been critical for. about two years and has experienced 28 such trips. The frequency has decreased to one trip -in -one to Problems have been experienced in maintaining the environmental two months.
temperature w.ithin acceptable limits and with electrical noise _ induced by defective cables. The. air condit'ioning equipment has oeen modified and the The de-temperature monitoring equipment and controls have been improved.
fective cable sections have been replaced.
>Mr. T. M. Starr and Mr. T. Rezek, Combustion Engineering, discussed the software changes which had been made and the software change control process. _ Combustion Engineering has developed a highly structured and detailed software change pro-The process is documented in a Combustion Engineering topical, CEN-39.
cess.
.This procedure was approved by the NRC Staff during the review of ANO-2.
CEN-39 was followed. for all ANO-2 and San Onofre Nuclear Generating Station (SONGS) software changes.
It was noted that some problems have been encountered in the implementation of this document and that the NRC Staff and APL have Sof tware modifi-r.
' disagreed as to what is specifically subject to NRC review.
cations have been performed on the original (OL application) ANO-2 and SONGS 2 & 3 package. The most significant of the ANO-2 software modifications s
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3 ELECTRICAL SYSTEMS ~
FEBRUARY 24 & 25, 1981 GENERAL SESSION (CONT'D)
.were' program changes which' were designe'd to eliminate trip on spurious control
. element assembly drop signals.
The principal modification for the SONGS 2 & 3 application has been the use of improved models for the heat flux calculations.
Mr. 'W. Morris, NRC Staff, noted that the preoperational tests are' adequate based upon ANO-2 experience and that the NRC Staff will audit the results.
He mentioned that the use of the data link between the CPC _and the plant computer is still a point of dispute.
The Arkansas Powar and Light Company
( APL) had agreed in the course of.the OL review to use the data link inter-connection be'treen the CPC and the plant computer only during the startup test program and to disconnect the data link within 10 days of the termination Hof the startup test _ program.
Subsequent to this, APL requested in a September 3,,
1980 letter to the NRC, that this data link be retained.
NRC did not ' respond to this request.and APL interpreted the NRC's silence as concurrer.ce and left.
the data link interconnection in place.
The ma:ter is under discussion.
Mr. L. Phillips, NRC Staff, discussed the status of the San Onofre review.
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He listed the milestones of the review and the tentative schedule. He also stated SONGS' commitment to obtain an independent review of software changes by a " qualified consultant" and to provide documentation of the final soft-ware design. There was considerable discussion regarding the definition of a " qualified consultant" and wnat would constitute adequate experience.
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' FEBRUARY.24 & 25, 1981
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cThe NRC Staff.has utilized the results of the extensive review l performed for. the ANO-2 appliestion and its ' review.of the ' SON 35 2 & 3 CP. Only the
.softwar'e and systems changes from the ANO-2 design are to be reviewed. ~The revi_ew is _in progress and is er.pected to be completed' in the near future.
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The meeting adjourne:: ~ at 5:25Ip.m..
FEBRUARY 25,' 1981 (CLOSED)
EXECUTIVE SESSI_011 "0?E9:
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N01E: For additional detail,s, a complete transcri;;t of the meeting is available in the NRC Publig Document Room,1717 H St., NW, Washington, DC 20555 or from Alderson Rep rters, -300 7th St., SW, Washington, DC, (202) 554-2345.
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PROPOSED AGENDA 24-25 Feb 1381 ELECTRICAL SYSTEMS SUBCOMMITTEE
. FEBRUARY 24, 1981 9:00
.9:15
.-. EXECUTIVE SESSION 2.
Description of the CE Core Protection Calculator and Comparison 9:15 -11:15-of the ANO-2 and San Onofre 2&3 Designs (2 hrs) - CE 3.
Discussion of ANO-2 Experience (2 hrs) - Arkansas Power & Light 11:15 - 1:15 1:15 - 2:15 LUNCH 4.
San Onofre 2&3 Core Protection Calculator (1 hr) - SCE and CE 2:15 - 3:15
. a) Summary of San Onofre Design and Test and Verification Program b) System modifications Use of ANO-2 Experience, and Bases 5.
'NRC Review of the San Onofre Core Protection Calculator 3:35 - 4:15 (1 hr) - NRC 6.
Comment by Southern California Edison Company, Arkansas Power 4:15 - 4:45 and Light Company, and Combustion Engineering 4:45 - 5:15 7.
GENERAL DISCUSSION 9
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FEBRUARY 25, 1981 DISCUSSIONS RELATING TO THE USE OF COMPUTER PROTECTION SYSTEMS AND CAN 9:00 - COB
- REGULATORY REQUIREMENTS FOR REACTOR CONTROL SYSTEMS............
Specific questions to be addressed by the NRC Staff as per Dr. Kerr's 12 Feb 81 request:
What has been the experience with the use of the data link between the CPC and 1) the plant computer and how would the NBC relate this experience to the NRC's current position on the use of this device?
What is ths status of the NRC actions on Arkansas Power and Light request for 2) the ccntinued use of the data link between the CPC and the plant compute,r?
- 3) How'did the review procedures used for the ANO-2 review differ from the San Onofre 2&3 revi.ew? Were features of the. San Onofre 2&3 design addressed which were not a'ddressed in the ANO-2 review?
Will a FMEA be performed for the San ONofre 2&3 Core Protection Calculater?
4)
If not, what-is the basis for the dccision?
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