ML18030A357

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Forwards Comments on NUREG-0801, Evaluation Criteria for Detailed Control Room Design Review. Consideration in Preparation of Final Documentation Requested
ML18030A357
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 12/23/1981
From: Curtis N
PENNSYLVANIA POWER & LIGHT CO.
To: Greenberg M
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0801, RTR-NUREG-801 PLA-982, NUDOCS 8201060535
Download: ML18030A357 (3)


Text

REGULATORY lNFORYATICN DISTRIBUTION SYSTEMS (RIDS)

ACCESSION NBR:8201060535 OQC ~ DATE: 81/12/23 NOTARIZED:

NO FACIL:50-387 Susquehanna S team Fl ectric Stati one Unit 1F Pennsyl va 50-388 Susquet arna Steam Electric Station<

Unit 2< Pennsylva AUTH.b At~E AUTHOR A FF ILI ATION'URTISF N ~ 8 ~

Pennsylvania Power 8 Light Co.

REC IP ~ NAl<E REC IP IEN I AFFILIATION GREENRERGFih, Division of Human Factors Safety SLBJECT:

Forwards comments on IIUREG-0801'Evaluation Criteria for Oetailea Control Hoor Design Review." Ccnsideration in preparation of final documentation requesteo

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TITLE: General Distr ibution for af ter Issuance of Operating License DOCKET 0500 7

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Pennsylvania Power 8 Light Company Two North Ninth Street

~ Allentown, PA 18101

~ 215 I 770.5151 Norman W. Curtis Vice President-Engineering

& Construction-Nuclear 215/ 770-5381 December 23, 1981 Mr. Marcus Greenberg Division of Human Factors Safety Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 8

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8 l4 frAMlamttgtt tewel trt."mfe~m8tf It TIOC SUSQUEHANNA STEAM ELECTRIC STATION COMMENTS ON NUREG 0801 ER 100450 FILE 841-2 PLA-982 841-9 DOCKET NOS.

50-387 AND 50-388

Dear Mr. Greenberg:

Enclosed are PP&L's comments on NUREG 0801 Evaluation Criteria for Detailed Control Room Design Review.

Please take them under considera-tion in preparation of final documentation on this subject.

Very truly yours, N.

W. Curtis Vice President-Engineering

& Construction-Nuclear RTJ:mp 442118 Enclosures SS 8~

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OR pO BEDOG P

COMMENTS ON'UREG 0801 It may be wrong to assume that the task analysis performed for NUREG 700 can be a basis for determining operator training and staffing needs, determining what information is needed for the Safety Parameter Display System and developing emergency operating procedures.

Each is a distinct evolution and should be addressed on its own requirments.

What is the purpose of site visits?

Will they attempt to validate portions of the program plan written into NUREG 700 or will the NRC (based on its review of preliminary plan submitted by the utility) provide specific guidance to that utility on portions of the utility plan found to be lacking by the NRC'?

It is not clear how to incorporate cost effectiveness evaluations into scheduling.

Enhancements may provide a significant, long-term improvement, while providing a cost effective solution which does not meet the "letter" of the guidelines in NUREG 700.

The NRC should consider delaying decision on a schedule to change control room designs until the results of evaluations of operation performance based on enhanced systems can be evaluated.

It is not apparent from NUREG 0801 that enough serious consideration is being given to the effect of many changes.

While each individual change to meet the guidelines may improve system operability, operators may be unfairly asked to re-learn too many control schemes from an unrealistic schedule for improvements.

This is not clearly called out in the guidelines for scheduling even though in defining HEDs, cumulative effects are to be considered.

mp/442118