ML20004D877

Forwards Draft Safety Evaluation of Response to SEP Topic VI-7.B, Engineered Safety Feature Switchover. No Change Recommended in Plant Instrumentation

ML20004D877
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	06/04/1981
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
TASK-06-07.B, TASK-6-7.B, TASK-RR LSO5-81-06-015, LSO5-81-6-15, NUDOCS 8106100257
Download: ML20004D877 (6)

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F June 4, 1981 Docket No. 50-155 I# /

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Mr. David P. Hoffman JU//

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Nuclear Licensing Administrator Consumers Power Company 1945 W Parnall Road L

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SUBJECT:

SEP TOPIC VI-7.8 ESF SWITCHOVER BIG ROCK POINT The enclosed draft safety evaluation report is based on the information provided by your May 11,1981 letter responses to previous staff ques-tions. Our report recorrends no change in plant instrumentation.

You are requested to review the enclosed report and to provide us with your comments, if any, within 30 days of receipt of this lett.er. This topic assessment may be revised in the future if your facility design is changed or if NRC criteria relating to this topic are modified before the integrated assessment is completed.

Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch No. S Division of Licensing

Enclosure:

As stated cc w/ enclosure:

See next page 8106100)87

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Docket No. 50-155 LS05 06-015 Mr. David P. Hoffman Nuclear Licensing Administrator Consumers Powei Company 1945 W Parnall Road Jackson, Michigan 49201

SUBJECT:

SEP TOPIC VI-7.8, ESF SWITCH 0VER BIG ROCK POINT The enclosed draft safety evaluation. report is based on the information provided by your May 11, 1981 letter responses to previous staff ques-tions. - Our report recommends no change in plant instrumentation.

You are requested to review the enclosed report and to provide us with your comments, if any, within 30 days of receipt of this letter. This topic assessment may be revised in the r'uture if your facility design is

. changed or if NRC criteria relating to this topic are modified before the integrated assessment is completed.

Sincerely,

%d?Ch' 4.

Dennis M. Crutchfiel'd, Ch Af Operating Reactors Branc No. 5 Division of Licensing

Enclosure:

As stated cc w/ enclosure:

See next page e-4 r>

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Mr. David P. Hoffman cc Mr. Paul A. Perry, Secretary U. S. Envircamental Protection Consumers Power Company Agency 212 West Michigan Avenue Federal Activities Branch Jackson, Michigan 49201 Region V Office ATTN: EIS COORDINATOR Judd L. Bacon, Esquire 230 South Dearborn Street Consumers Power Company Chicago, Illinois 60604 212 West Michigan Avenue Jack son, Michigan 49201 Herbert Grossman, Esq., Chairmai Atomic Safety and Licensing Bord Joseph Gallo, Esquire U. S. Nuclear Regulatory Commisdon Isham, Lincoln & Beale Washington, D. C.

20555 1120 Connecticut Avenue Room 325 Dr. Oscar H. Paris Washington, D. C.

20036 Atomic Safety and Licensing Boed U. S. Nuclear Regulatory Cocnission Peter W. Steketee, Esquire Washington, D. C.

20555 505 Peoples Building Grand Rapids, Michigan 49503 Mr. Frederick J. Shon Atomic Safety and Licensing Bord:

Alan S. Rosenthal. Esq., Chairman U. S. Nuclear Regulatory Commision Atomic Safety & Licensing Appeal Board Washington, D. C.

20555 U. S. Nuclear Regulatory ComMssion Washington, D. C.

20555 Big Rock Point Nuclear Power Phnt ATTN: Mr. C. J. Hartman Mr. John O'Neill, II Plant Superintendent Route 2, Box 44 Charlevoix, Michigan 49720 Maple City, Michigan 49664 Christa-Maria Charlevoix Public Library Route 2, Box 108C 107 Clinton Street Charlevoix, Micnigan 49720 Charlevoix, Michigan William J. Scanlon, Esquire Chairman 2034 Pauline Boulevard County Beard of Supervisors Ann Arbor, Michigan 48103 Charlevoix County Charlevoix, Michigan 49720 Pesident Inspector Big Rock Point Plant Office of the Governor (2) c/o U.S.'NRC Room 1 - Capitol Building RR #3, Box 600 Lansing, Michigan 48913 Charlevoix, Michigan 49720 Director, Criteria and Standards Mr. Jim E. Mills Division Route 2 Box 103C Office of-Radiation Programs Charlevoix, Micnigan 49720 (ANR-460)

U. S. Environmental Protection Thomas S. Moore Agency Atomic Safety & Licensing AppealBoard Washington, D. C.

20460 U. S. Nuclear Regulatory Commisfon Washington, D. C.

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BIG ROCK POINT PLANT SEP TOPIC VI-7.B., ESF SWITCH 0VER TOPIC VI-7.B:

ESF (ENGINEERED SAFETY FEATURES) SWITCHOVER FROM INJECTION TO RECIRCULATION MODE, AUTOMATIC ECCS REALIGNMENT - BIG ROCK POINT I.

Introduction Most Pressurized Water Reactors (PWRs) require operator action to realign the ECCS _ for the recirculation mode following a LOCA. The NRC staff has been requiring, on a case-by-case basis, some automatic features to assist in the realignment of the ECCS from the injection to the recirculation mode of operation.

The safety objective of this requirement is to increase the reliability of.long-term cooling by_ reducing the number of operator actions required to change system realignment to the recirculation mode.

Although Big Rock Point.is a Boiling Water Reactor (B$R), this ~ topic is applicable to this plant because ECCS water is initially supplied by the fire protection system.

Failure to terminate the introduction of fire water in a timely manner will result in containment flooding. Such floodTng could cause the loss of safety instrumentation and, ultimately, containment itsel f.

The scope of this topic requires a review of the ECCS control system and the operator action required to realign the ECCS from injection to recircula-

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tion mode following a LOCA. The sequence of events from. initiation of the injection mode to completion _of the recirculation made, the systems / components and instrumentation / controls utilized in the injection to recirculation pro-cess, and the automatic and/or manual process required to complete the switch-over process a re to be reviewed. The objective of this review is to determine if automatic switchover is necessary to protect public health and safety.

II.

Review Criteria The current licensing criteria which govern the safety issue ara, identified in Table 7-1 of the Standard Review Plan. The most significant of these criteria are:

1.

Branch Technical Position ICSB 20, 2.

IEEE Std 279 1971, and 3.

Regulatory Guide 1.62.

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III. Related Safety Topics and Interfaces The scope of review for this topic was limited to avoid duplication of effort since some aspects of the review wre performed under related topics. The related topics and the subject matter are identified below.

Each of the related topic report contains the acceptance crite'ria and review guidance for its subject matter.

III-6

- Seismic Design Considerations III-10.A

- Thermal-Overload Protection for Motor Operated Valves III-ll

- Component Integrity III-12

- Environmental Qualification IV-1.A

- Operation with less Than All Reactor Coolant Loops in Service V-10.8

- RHR Reliability V-11

- High Pressure / Low Pressure Interfaca VI-7.A.3

- ECCS Actuation System VI-7.C.1

- Independence of Onsite Power VI-10.A

- Testing of ESF Systems VI-10.8

- Shared Systems VIII-2

- Onsite Emergency Power Systems VIII-3

- Emergency de Systems' VIII-4

- Containment Penetrations The follcwing topics,are dependent on the present topic infomation for completion:

VI-4

- Containment Isolation System VI-7.C.2

- ECCS Single Failure Criterion IV.

Review Guidelines ICSB 20 states that automatic transfer to the recirculation mode is prefer-able to nanual transfer and should be provided for standard plant designs submitted for review on a generic basis under the Commission's standardi-zation policy.

ICSB 20 also states that a design that provides manual initiation at the system level of the transfer to the recirculation mode, while not ideal, is sufficient and satisfies the intent of IEEE Std 279 provided that adequate instrumentation and information display are available to the operator so that he can make the correct decision at the correct time. Furthermore, it should be shown that, in case of operator error, there are sufficient time and information available-so that the operator can co'rrect the error, and the consequences of such an error are acceptable.

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Evaluation Big Rock Point does not have an automatic transfer and it is not a standard plant submitted for review on a generic basis.

Accordingly..the staff limited its review to the instrumentation and controls that are used to terminate the injection phase of Emergency Core Cooling (ECCS).-

The staff's review of ECCS single failure (Topic VI-7.C.2) shows that there are no single failures beyond the failures considered in this topic that could result in the failure of more than one train of ECCS or result in unacceptable offsite doses.

Questions were sent to the~' licensee -in order to obtain sufficient information upon which to conduct an independent review.

As a result of the lice.;ee responses.the staff determined-that the ECCS injection mode is terminated by operator action upon receipt of a high containment level signal. This signal is derived from a single level transmitter and a redundant system of level switches that are powered from Class'1E buses. These instruments are not subject to freezing.

VI.

Conclusions

-The switchover from injection to recirculation in Big Rock Point 1s accomplished manually from the control room. The primary instruments for determining when to make the switchover satisfy the single failure criterion and ard acceptable.

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