ML20244B491

Notifies of Potential Problem Re Design Change at Facilities Affecting Responsibility for BWR 5/6 Control Rod Drive Scram Testing.Tests Are Sufficiently Important to Require Performance by Operating,Rather than Maint,Personnel

ML20244B491
Person / Time
Site:	LaSalle, 05000000
Issue date:	04/16/1981
From:	Blackwood E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To:	Reimann F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
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References
FOIA-87-121 NUDOCS 8104290518
Download: ML20244B491 (2)

Text

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MEMORANDUM FOR: F. Reimann, Acti.ng Chief, Reactor Projects.Section'10, i Region III FROM: E. B. Blackwood, Chief, Reactor Projects Section (RI & III),

DRRRI, IE

SUBJECT:

BWR 5/6 CONTROL ROD DRIVE SCRAM TESTING (AITS F03001881)

By memorandum dated January 16, 1981, R. L. Spessard forwarded a memo from Roger D. Walker, senior resident inspector at LaSalle County Nuclear Station.

Mr. Walker called attention to a change in design for LaSalle (and other BWR 5's and BWR 6's) which requires that' individual Control ' Rod Drive test in-sertions be performed locally at the hydraulic control units in the reactor building,.rather than from the control room, as for previous designs.

4 Mr. Walker -questions whether the letter or intent of 10 CFR Part 55 is violated by using someone other than a licensed operator for manipulations which affect reactivity, even in a negative manner. The licensed control room operator would perform individual rod withdrawal actions from the control room, but individual rod insertions for scram time testing can only be performed at the hydraulic control unit stations.

We have discussed this subject with Paul Collins, Chief, Operator Licensing Branch, NRR.- and have jointly come to the conclusion that, so long as the full

- time and attention of the licensed control room operator for the duration of the testing is dedicated to the testing, the intent of 10 CFR 55.4(d) is satis-fied, and that aspect of Mr. Walker's concern is resolved.

We are, however, concerned about another aspect of the situation. We have vua n ti h r cus n.ont'n3 ti u w.. e , icar vt v.rs y,L%c.,,o *.atemo: pr -

sonnel functions such -as the subject testing, which have historically been the responsibility of the operating staff. Mr. Walker advises us that such is the situation at LaSalle. Another example is the recent (January,1981) event at Palisades, where a member of the maintenance staff, on apparent completion of a required test action, actually left both battery banks isolated.

We recognize that there are many NRC requirements, such a.s protection system periodic calibrations, which ar6 performed by instrument technicians or other CONTACT: J, B. Henderson, IE 49-27551 1

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F. Reimann APR 1 f> 1331 maintena~nce personnel, however, we believe that for those activities the i operating staff should clear' the area for work (e.g. place one redundant channel in the trip mode), and shoe.d restore the equipment to service (reset the trip). Other actions such as the control

• rod drive-tests appear to us to be sufficiently important to require performance hy members of the operating staff. By this we do not racessarily mean only NRC licensed operators. Control rod drive testing, for example could well be done hy a trained auxiliary operator following explicit procedures in continuous telephonic contact with the control room operator. We intend to pursue this subject further with NRR.

E. 'B. Blackwood, Chief Reactor Projects Section (RI & III)

Division of Resident and Regional Reactor Inspection Office of Inspection and Enforcement cc: J. H. Sniezek, IE E. L. Jordan, IE R. L. Spessard, RIII '

P. Collins, NRR R. Campbell, NRR B. J. Youngblood, NRR f A. Bournia, NRR R. Walker, SRI LaSalle f

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