ML20062H485

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Motion for Summary Disposition of Jf Doherty Contention 12 Alleging Unreliability of Rod Pattern Control Sys.Alleged Failures of Various Instruments Do Not Relate to Purpose of Sys.Sys Is self-checking & Immune to Failure.Pp 61-64
ML20062H485
Person / Time
Site: Allens Creek File:Houston Lighting and Power Company icon.png
Issue date: 08/04/1980
From:
BAKER & BOTTS, HOUSTON LIGHTING & POWER CO., LOWENSTEIN, NEWMAN, REIS, AXELRAD & TOLL
To:
Atomic Safety and Licensing Board Panel
Shared Package
ML19331C559 List:
References
ISSUANCES-CP, NUDOCS 8008190066
Download: ML20062H485 (4)


Text

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i 4

lll UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION

,I BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of S

I S

HOUSTON LIGHTING & POWER S

COMPANY S

Docket No. 50-466

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S 6

(Allens Creek Nuclear S

l Generating Station, Unit S

l No. 1)

S 1

1 APPLICANT'S MOTION FOR

SUMMARY

f DISPOSITION ON INTERVENOR DOHERTY'S f

i CONTENTION NO. 12 1

Applicant moves the Board under 10 CFR S 2.749 to grant summary disposition with respect to Intervenor Doherty's Contention No. 12 relating to the alleged unreliability of the Rod Pattern Control System (RPCS).

As shown in the accompanying statement of material facts as to which there

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is no genuine issue to be heard, and the affidavit of Joseph F.

Lesyna there is no issue to try in this proceeding and

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Applicant is entitled under S 2.749 to have the contention j

summarily dismissed as a matter of law.

The Contention Doherty's Contention No. 12 states:

Intervenor contends the Rod Pattern Control System in the Instrument and Controls systems of the proposed ACNGS is not reliable.

The operators of Dresden Unit 3 La GE BWR) reported the system in-g 00819 0 066 61 L

l operable for 54 percent of start-ups in the start-ups, and Millstone Unit I reported this system failed in i

172 of 245 start-ups in a 16-month period beginning in 1971.

Further, 34.6 percent of " Reportable Occurrences" in BWR reactors in 1977 were in the Instrumentation and Controls area (NUREG-0483, p. 4-7).

The Average Power Range Monitor (APRM) used to detect surplus neutron flux in this system is not highly reliable.

Power Range Instruments contributed to 36 " Reportable Occurrences" in BWRs in 1977, and 17 in 1976, (Nuclear Safety, Volumes 19(1) and 20(1), 1978 and 1979, pp. 84 and 82, respectively).

Most recently a red block monitor was inoperative during start-up of the Brunswick-2 reactor (September 4, 1978) due to a failed integrated circuit.

Petitioners contend danger to their health and safety interest by a reactivity insertion accident during start-up unless Applicant installs a more reliable system than this one.

Argument i

Intervenor's argument that Applicant's Rod Pattern Control System is unreliable is based on a factually erroenous l

premise.

Intervenor presumes that instrumentation problems l

that occurred at older BWRs are applicable to the RPCS designed for Allens Creek.

Contrary to Intervenor assertions, there are significant design and operational differences between the

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systems and components which experienced some performance difficulties and the totally redesigned system to be installed in ACNGS.

The attached affidavit of Mr. Lesyna explains that Intervenor may have grounds for faulting the older Rod Worth Minimizer (RWML system, but that there are no analogous grounds applicable to the new RPCS.

The RWM is a single-channel computer (U3

1 i

system which takes rod position inputs from single detectors and compares them against a " software" programmed memory; the system is easily manipulated or completely bypassed.

The RPCS system is a dual-channel computer system i

which takes rod position inputs from dual detectors and q

compares them against a hardwired memory locked in electronic l

i I

circuit cards; the system cannot be altered except by the improbable course of " rewiring" and it cannot be completely bypassed.

i A reactor startup cannot proceed unless the RPCS is completely operable.

The failure of any component within the RPCS system will interrupt " permissive" signals; without these permissive signals, it is not possible to generate rod movement signals to the control rod hydraulic drives.

Therefore, any failure--or "unreliability"--in the system will result in I

the inability to move rods, but will not prevent shutting down the reactor through a reactor trip (SCRAM).

Moreover, the RPCS cannot be completely bypassed, as was the case with the RWM system.

To avoid unnecessary operating restrictions, it is possible to substitute input signals for a very small number of failed inputs from inoperable position detectors or failed drives.

The number of substitutions is operationally and systematically limited to guarantee that deleted inputs will not produce unacceptable rod patterns..

p.

EU3

I The sole purpose of the RPCS is to limit the reactivity I

worth of individual control rods by restricting rod movement to predetermined patterns or sequences.

These patterns have in turn been conservatively analyzed to assure that the associated worst-case reactivity addition accident (rod drop) does not exceed appropriate limits.

Finally, Intervenor's disjointed citations to alleged failures in various instruments (Average Power Range Monitors, Rod Block Monitors, etc.) totally miss the mark:

i these components and systems have nothing to do with the purpose or functioning of RPCS.

Moreover, as noted above, any any RPCS failure automatically produces a safe condition in that rods cannot be moved at all and certainly not into unacceptable patterns.

The RPCS is self-checking and immune to hazardous failures.

Accordingly, there is no genuine issue of material l

fact to be tried in this proceeding, and Applicant is entitled j

to summary disposition as a matter of law.

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