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=Text=
=Text=
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{{#Wiki_filter:4 s.
June 22,1982 Dw:ket No. 50-155 L505-82 076 s
Mr. David J. VandeWalle Nuclear Licensing Administrator Consumers Power Company 1945 W Parnall Road Jaelson, Michigan 49201
 
==Dear Mr. VandeWalle:==
==SUBJECT:==
SEP TOPIC VIII-2, ONSITE EMERGENCY POWER SYSTEMS - DIESEL GENERATOR, FINAL SAFETY EVALUATION FOR BIG ROCK POINT is our contractor's final Technical Evaluation Report on this topic for your facility. is a revised Safety Evaluation Report based on Enclosure 1. has been revised to reflect the additional information provided in the {{letter dated|date=April 21, 1982|text=April 21, 1982 letter}} from R. Vincent to D. Crutchfield.
As a result of the additional infomation you have provided, the staff has concluded that the diesel generator output frequency may be too low under accident loading conditions. The staff, therefore, requires that the transient frequency bc justified by test or analysis or the diesel modified to provide a quicker speed control system.
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.
l Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 l-Division of Licensing
 
==Enclosure:==
As stated M
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See next page 0
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.Mr. David 'J. Vand:Walle CC Mr. Paul A. Pe'rry, Secretary U. S. Environmental Protection Consumers Power Company Agency 212 West Michigan Avenue Federal Activities Branch Jackson, Michigan 49201 Region V Office ATTN:
Regional Radiation Representative Judd L. Bacon, Esquire 230 South Dearborn Street Consumers Power Company Chicago, Illinois 60604 212 West Michigan Avenue Jackson, Michigan 49201 Peter B. Bloch, Chairman Atomic Safety and Licensing Board Joseph Gallo Esquire U. S. Nuclear Regulatory Commission Isham, Lincoln 'A Beale Washington, D. C.
20555 1120 Connecticut Avenue Room 325 Dr. Oscar H. Paris Washington, D. C.
20036 Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Peter W. Steketee, Esquire Washington, D. C.
20555 505 Peoples Building Grand Rapids, Michigan 49503 Mr. Frederick J. Shon
~
Atomic Safety and Licensing Board Alan S. Rosenthal Esq., Chaiman U. S. Nuclear Regulatory Commission Atomic Safety & Licensing Appeal Board Washington, D. C.
20555 U. S. Nuclear Regulatory Cimmission Washington, D. C.
20555 Big Rock Point Nuclear Power Plant ATTN: Mr. C. J. Hartman Mr. John O'Neill, II Plant Superintendent Route 2, Box 4(
Charlevoix, Michigan 49720 Maple City, Michigan 49664 Christa-Maria Mr. Jim E. Mills Route 2, Box 108C Route 2, Box 108C Charlevoix, Michigan 49720 Charlevoix, Michigan 49720 William J. Scanlon, Esquire Chairman 2034 Pauline Boulevard County Board of Supervisors Ann Arbor, Michigan 48103 Charlevoix County Charlevoix, Michigan 49720 Resident Inspector Big Rock Point Plant Office of the Governor (2) c/o U.S. NRC l
Room 1 - Capitol Building RR #3, Box 600 Lansing, Michigan 48913 Charlevoix, Michigan 49720 Herbert Semel Counsel for Christa Maria, et al.
Urban Law Institute Antioch School of Law 263316th Street, NW Washington, D. C.
20460
~
i l
 
7 s
a Mr. David J. VandeWalle cc Dr. John H. Buck Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission x_
Washington, D. C.
20555 Ms. JoAnn Bier 204 Clinton Street Charlevoix, Michigan 49720' Thomas S. Moore Atomic Safety and Licensing Appeal Board U. S Nuclear Regulatory Commission Washington, D. C.
20555
~
James G. Keppler, Regional Administrator Nuclear Regulatory Commission, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 W
:)
i
~
i O
e e
 
~
SYSIEMATICEVALUATIONPROGRAM TOPIC VIII-2
, BIG ROCK POINT TOPIC: VIII-2, ONSITE EMERGENCY POWER SYSTEMS - DIESEL GENERATOR I.
Introduction lif esel penerators, which provide emergency standby power for safe reactor shutdowi in the event of total loss of offsite power, have experienced a significant number of failures. The failures to date have been attributed to a variety of causes, including failure of the air startup, fuel oil, and combustion air systems.
In some instances, the malfunctions were due, The information available to the control room operator to to lockout.
indicate the operational status of the diesel generator was imprecise and could lead to misinterpretation. This was caused by the sharing of a single annunciator station by alarms that indicate conditions that render a diesel generator unable to respond to an. automatic cmergency start signal and alarms that only indicate a warning of abnormal, but no disabling, conditions. Another cause was the wording on an annunciator window which did not specifically say that the diesel generator was inoperable (i.e.,
unable at the time to respond to an automatic emergency start signal) l_
when in fact it was inoperable for that purpose. The review included the reliability, protective interlocks, fuel oit quality, and testing of diesel generators to assure that the diesel generator meets the avail-ability requirements for providing emergency standby power to the engineered safety features.
II.
Review Criteria The review criteria are presented for Section 8.3.1 in Table 8-1 of the Standard Review Plan.
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 were performed under related Related topics and the subject matter are. identified below.
topics.
Each of the related topic reports contain the acceptance criteria.and review guidance for its subject matter.
III-12 Environmental Qualification VI-7.C.1 Independence of Onsit6 Power VIII-1.A Degraded Grid e
XVII Fuel Oil Quality Assurance There are no safety topics that.are dependent in the present topic informa ''
: (_
tion for their completion.
e b
,-,,_,.___.-_m,
~.
 
. IV.
Review Guidelines The review guidelines are presented in Section 8.3.1 of the Standard Review Plan.
V.
Evaluation The concern with regard to. annunciators was pursued as a generic issue.
The staff safety evaluation concluded that in order to provide the operator with accurate, complete and timely information pertinent to the status of the diesel generators, as required by IEEE Std. 279-1971, the following corrective actions are required:
1.
Disabling and non-disabling conditions, currently alarmed at a common annunciator station, should be separated and annunciated at separate annunciator points.
2.
The wording on the annunciator for disabling conditions should
~
specifically state that the diesel generator is unavailable for an automatic emergency start.
By a {{letter dated|date=May 11, 1978|text=letter dated May 11, 1978}}, the licensee agreed to make suitable modifications to the annunciators.
Also, as a result of the work done by the University of Dayton, a t
generic program for implementing most of the recommendations forre-liability enhancement that are contained in the University of Dayton report is being conducted by NRC. This latter program will also determine the adequacy of the diesel generator. testing program on a case-by-case basis and enforce any necessary changes.
The question of fuel oil quality was addressed on a generic basis in January 1980, by letters to all licensees.
The letters required that licensees include fuel oil in their Quality Assurance program. The Quality Assurance program is addressed in Topic XVII. Until completion of Topic XVII, the periodic testing of the diesels is considered to be an adequate interim method for assuring acceptable quality in the fuel oil stored on site.
i Beyond these efforts, EG&G Report EGG-EA-5882, " Diesel Generator Big Rock Point" presents a technical evaluation of the diesel generator protective interlocks and load capability at Big Rock Point against present licensing criteria.
The report notes that the protective trips are in agreement with current NRC guidelines, but that the output
[
frequency is too low during tha loading of the fire pump.
l
' ' ' ' ~ ~~
=---.
 
2-VI.
Conclusion The staff finds that the diesel generator protective interlocks are
' acceptable, but the low output frequency muit be justified by test or analysis or the diesel generator speed control improved.
i 4
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Latest revision as of 17:13, 17 December 2024

Forwards Revised Safety Evaluation of SEP Topic VIII-2, Onsite Emergency Power Sys - Diesel Generator, Based on Eg&G Final Technical Evaluation Rept.Diesel Generator Output May Be Too Low Under Accident Loading Conditions
ML20054K041
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 06/22/1982
From: Crutchfield D
Office of Nuclear Reactor Regulation
To: Vandewalle D
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
Shared Package
ML20054K042 List:
References
TASK-08-02, TASK-8-2, TASK-RR LSO5-82-06-076, LSO5-82-6-76, NUDOCS 8206300330
Download: ML20054K041 (6)


Text

4 s.

June 22,1982 Dw:ket No. 50-155 L505-82 076 s

Mr. David J. VandeWalle Nuclear Licensing Administrator Consumers Power Company 1945 W Parnall Road Jaelson, Michigan 49201

Dear Mr. VandeWalle:

SUBJECT:

SEP TOPIC VIII-2, ONSITE EMERGENCY POWER SYSTEMS - DIESEL GENERATOR, FINAL SAFETY EVALUATION FOR BIG ROCK POINT is our contractor's final Technical Evaluation Report on this topic for your facility. is a revised Safety Evaluation Report based on Enclosure 1. has been revised to reflect the additional information provided in the April 21, 1982 letter from R. Vincent to D. Crutchfield.

As a result of the additional infomation you have provided, the staff has concluded that the diesel generator output frequency may be too low under accident loading conditions. The staff, therefore, requires that the transient frequency bc justified by test or analysis or the diesel modified to provide a quicker speed control system.

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.

l Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 l-Division of Licensing

Enclosure:

As stated M

o cc w/ enclosure:

See next page 0

9206300330 820622

[

lDR ADOCK 05000155 PDR j

f

, y omc.,.... S

,S EPB,:

SE 3:DL

, ORB #5:PM OR C,,,

D,L,

.. 8u.s.s.eu....8.Emcht. pm.c,Mhne,H

.ua~c >

.:n...nennam..

W

....GL A..n s.,,..

6

.. 0../82

. sf.g/82......

e.gze2...

6

.gs2.....,....ely.az....

em>

l yac ronu sie oa80) NRCM 0.xo OFF1ClAL RECORD COPY

\\

usa m i.ei-m e

.x..,

.Mr. David 'J. Vand:Walle CC Mr. Paul A. Pe'rry, Secretary U. S. Environmental Protection Consumers Power Company Agency 212 West Michigan Avenue Federal Activities Branch Jackson, Michigan 49201 Region V Office ATTN:

Regional Radiation Representative Judd L. Bacon, Esquire 230 South Dearborn Street Consumers Power Company Chicago, Illinois 60604 212 West Michigan Avenue Jackson, Michigan 49201 Peter B. Bloch, Chairman Atomic Safety and Licensing Board Joseph Gallo Esquire U. S. Nuclear Regulatory Commission Isham, Lincoln 'A Beale Washington, D. C.

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

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

20555 505 Peoples Building Grand Rapids, Michigan 49503 Mr. Frederick J. Shon

~

Atomic Safety and Licensing Board Alan S. Rosenthal Esq., Chaiman U. S. Nuclear Regulatory Commission Atomic Safety & Licensing Appeal Board Washington, D. C.

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

20555 Big Rock Point Nuclear Power Plant ATTN: Mr. C. J. Hartman Mr. John O'Neill, II Plant Superintendent Route 2, Box 4(

Charlevoix, Michigan 49720 Maple City, Michigan 49664 Christa-Maria Mr. Jim E. Mills Route 2, Box 108C Route 2, Box 108C Charlevoix, Michigan 49720 Charlevoix, Michigan 49720 William J. Scanlon, Esquire Chairman 2034 Pauline Boulevard County Board of Supervisors Ann Arbor, Michigan 48103 Charlevoix County Charlevoix, Michigan 49720 Resident Inspector Big Rock Point Plant Office of the Governor (2) c/o U.S. NRC l

Room 1 - Capitol Building RR #3, Box 600 Lansing, Michigan 48913 Charlevoix, Michigan 49720 Herbert Semel Counsel for Christa Maria, et al.

Urban Law Institute Antioch School of Law 263316th Street, NW Washington, D. C.

20460

~

i l

7 s

a Mr. David J. VandeWalle cc Dr. John H. Buck Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission x_

Washington, D. C.

20555 Ms. JoAnn Bier 204 Clinton Street Charlevoix, Michigan 49720' Thomas S. Moore Atomic Safety and Licensing Appeal Board U. S Nuclear Regulatory Commission Washington, D. C.

20555

~

James G. Keppler, Regional Administrator Nuclear Regulatory Commission, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 W

)

i

~

i O

e e

~

SYSIEMATICEVALUATIONPROGRAM TOPIC VIII-2

, BIG ROCK POINT TOPIC: VIII-2, ONSITE EMERGENCY POWER SYSTEMS - DIESEL GENERATOR I.

Introduction lif esel penerators, which provide emergency standby power for safe reactor shutdowi in the event of total loss of offsite power, have experienced a significant number of failures. The failures to date have been attributed to a variety of causes, including failure of the air startup, fuel oil, and combustion air systems.

In some instances, the malfunctions were due, The information available to the control room operator to to lockout.

indicate the operational status of the diesel generator was imprecise and could lead to misinterpretation. This was caused by the sharing of a single annunciator station by alarms that indicate conditions that render a diesel generator unable to respond to an. automatic cmergency start signal and alarms that only indicate a warning of abnormal, but no disabling, conditions. Another cause was the wording on an annunciator window which did not specifically say that the diesel generator was inoperable (i.e.,

unable at the time to respond to an automatic emergency start signal) l_

when in fact it was inoperable for that purpose. The review included the reliability, protective interlocks, fuel oit quality, and testing of diesel generators to assure that the diesel generator meets the avail-ability requirements for providing emergency standby power to the engineered safety features.

II.

Review Criteria The review criteria are presented for Section 8.3.1 in Table 8-1 of the Standard Review Plan.

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 were performed under related Related topics and the subject matter are. identified below.

topics.

Each of the related topic reports contain the acceptance criteria.and review guidance for its subject matter.

III-12 Environmental Qualification VI-7.C.1 Independence of Onsit6 Power VIII-1.A Degraded Grid e

XVII Fuel Oil Quality Assurance There are no safety topics that.are dependent in the present topic informa

(_

tion for their completion.

e b

,-,,_,.___.-_m,

~.

. IV.

Review Guidelines The review guidelines are presented in Section 8.3.1 of the Standard Review Plan.

V.

Evaluation The concern with regard to. annunciators was pursued as a generic issue.

The staff safety evaluation concluded that in order to provide the operator with accurate, complete and timely information pertinent to the status of the diesel generators, as required by IEEE Std. 279-1971, the following corrective actions are required:

1.

Disabling and non-disabling conditions, currently alarmed at a common annunciator station, should be separated and annunciated at separate annunciator points.

2.

The wording on the annunciator for disabling conditions should

~

specifically state that the diesel generator is unavailable for an automatic emergency start.

By a letter dated May 11, 1978, the licensee agreed to make suitable modifications to the annunciators.

Also, as a result of the work done by the University of Dayton, a t

generic program for implementing most of the recommendations forre-liability enhancement that are contained in the University of Dayton report is being conducted by NRC. This latter program will also determine the adequacy of the diesel generator. testing program on a case-by-case basis and enforce any necessary changes.

The question of fuel oil quality was addressed on a generic basis in January 1980, by letters to all licensees.

The letters required that licensees include fuel oil in their Quality Assurance program. The Quality Assurance program is addressed in Topic XVII. Until completion of Topic XVII, the periodic testing of the diesels is considered to be an adequate interim method for assuring acceptable quality in the fuel oil stored on site.

i Beyond these efforts, EG&G Report EGG-EA-5882, " Diesel Generator Big Rock Point" presents a technical evaluation of the diesel generator protective interlocks and load capability at Big Rock Point against present licensing criteria.

The report notes that the protective trips are in agreement with current NRC guidelines, but that the output

[

frequency is too low during tha loading of the fire pump.

l

' ' ' ' ~ ~~

=---.

2-VI.

Conclusion The staff finds that the diesel generator protective interlocks are

' acceptable, but the low output frequency muit be justified by test or analysis or the diesel generator speed control improved.

i 4

b

' ' ~ ^

w'

'