ML17250A851

Forwards Draft Technical Evaluation of SEP Topic VIII-2, Diesel Generators. Evaluation Will Be Basic Input to Integrated Safety Assessment for Facility

ML17250A851
Person / Time
Site:	Ginna
Issue date:	12/12/1980
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	White L ROCHESTER GAS & ELECTRIC CORP.
References
TASK-08-02, TASK-8-2, TASK-RR LSO5-80-12-030, LSO5-80-12-30, NUDOCS 8101070476
Download: ML17250A851 (20)

Text

.,,.,)) (iye) ( P$I;gg.

Docket No. 50-244 LS05"80-12-030 Mr. Leon D. White, Jr.

Vice President Electric and Steam Production Rochester Gas 8 Electric Corporation 89 East Avenue Rochester,'ew York 14649

Dear Mr. White:

D ISTRI BUTION:

0 IE (3)

NRC PDR 'Crutchfield LPDR RSnaider TERA HSmith NSIC ACRS (16)

NRR RF JHeltemes ORB ¹5 RF GCwalina DEGEhIB<R 1 2 1980 DEisenhut Gray File RPurple SEP File 2

TNovak OELD GLainas J Roe CBerl.inger BHerrmann 3 H RScholl R

4 I

t%3 RE:

SEP.

TOPICS VIII-2,'IESEL GENERATORS-- R. E. GINNA NUCLEAR POWER PLANT Enclosed is a copy of our current evaluation of SEP Topic VIII-2, Diesel Generators for R. E. Ginna Nuclear Power Plant.

This assessment compares your facility, as described in Docket No. 50-244, with the criteria currently used by the regulatory staff'for licensing new facilities.

Please inform us if your as-built facility differs from the licensing basis assumed in our assessment-Coments received by January 30, 1981 will be included in our final report-This evaluation will be a basic input to the integrated safety assessment for your facility unless you identify changes needed to reflect the as-built conditions at your facility. 'This assessment may be revised in the future if your facility design is changed or if NRC criteria relating to this subject are rmdified before the integrated assessment is completed.

In.future correspondence regarding this topic, please refer to the topic number in your cover letter.

Sincerely, Crie,inal signed by Dennis M. Crutchfield

Enclosure:

Draft SEP Topic VIII-2 cc w/enclosure:

See next pag 6101 0'F0 Dennis M. Crutchfield, Chief Operating Reactors Branch ¹5 Division of Licensing OFFICE)

SURNAME 0ATE)

L:

RB ¹5JPM RSnaider:rj f~ /i~/so p: +$5/LA H

t

~-j diso DL:SEPB/C WTRussell (v / (q/80 DL:

C.....

DC tchfield tZ,/IN80 NRC FORM 318 (9.761 NRCM 0240 AU.S. GOVERNMENT PRINTING OFFICE: 1979 289 369

0 wJ4,4

!:).r '<<i,"j;Efra.')4 fU/) fbffZA fr'f' f'ffj'forrgg

.'l I 'f 5<<f. f r"<<

el'r:f. 0".'.

J<<I<<'f,'f

&>>"f'Tu"t.

4

<<I Ll

<<'I r

~H

<<f. vt 3>l 2>; SiV i!~<<P;-iaaf'.i +<<

.f',;~f N A6VG<< f 26fff6Jt)

~] <<trrtf! f f/<<g<",J I

s 9 jjfJ.<<.

-ln 4

I I

Ij Jj, Kjl II,<<

7 IX

-4, I I

4 55'l k

44 I ~

I

-g

<<4 t

I ~ tl

~.rf l

, 4 I

Il 5

Fg

-4 J 4

UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 December 12, 1980 Docket No. 50-244 LS05-80-12-030 Mr. Leon D. White, Jr.

- Vice President Electric and Steam Production Rochester Gas 5 Electric Corporation 89 East Avenue Rochester, New York 14649

Dear Mr. White:

RE:

SEP TOPIC VIII-2, DIESEL GENERATORS - R. E. GINNA NUCLEAR POWER PLANT Enclosed is a copy of our current evaluation of SEP Topic VIII-2, Diesel Generators for R. E. Ginna Nuclear Power Plant.

This assessment compares your facility, as described in Docket No. 50-244, with the criteria currently used by the regulatory staff for licensing new facilities-Please inform us if your as-built facility differs from the licensing basis assumed in our assessment.

ComIents received by January 30, 1981 will be included in our final report.

This evaluation will be a basic input to the integrated safety assessment for your facility unless you identify changes needed to reflect the as-built conditions at your facility.

This assessment may be revised in the future if your facility design is changed or if NRC criteria relating to this subject are rmdified before the integrated assessment is completed.

In future correspondence regarding this topic, please refer to the topic number in your cover letter..

Sincerely,

Enclosure:

Draft SEP Topic VIII-2 Dennis M. Crutchfield, hief Operating Reactors Branch 85 Division of Licensing cc w/enclosure:

See next page

Mr. Leon D. White, Jr.

December 12, 1980 cc w/enclosure(s):

Harry H. Voigt, Esquire LeBoeuf, Lamb, Leiby and NacRae 1333 New Has@shire

Avenue, N. M.

Suite 1100 Mashington, D. C.

20036 Nr. Michael Slade 12 Trailwood Circle Rochester, New York 14618 Rochester Coomittee for Sci entific Information Robert E. Lee, Ph.D.

P. 0. Box 5236 River Campus Station Rochester, New York 14627 Jeffrey Cohen New York State Energy Office Swan Street Building Core 1, Second Floor Empire State Plaza Albany, New York 12223 Director, Technical Development Programs State of New York Energy Office Agency Building 2 Empire State Plaza Albany, New York 12223 Rochester Public Library 115 South Avenue Rochester, New York 14604 Supervisor of the Town of Ontario 107 Ridge Road West

Ontario, New York 14519 Resident Inspector R. E. Ginna Plant c/o U. S.

NRC 1503 Lake Road

Ontario, New York

- 14519 Ezra I. Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 0 irector, Criteri a and Standards Division Office of Radiation Programs (ANR-460)

U. S. Environoantal Protection'gency Mashington.

D. C.

20460 U. S. Environmental Protection Agency Region II Office ATTN:

EI S COORD INATOR 26 Federal Plaza New York, New York 10007 Herbert Grossman, Esq.,

Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comnission Mashington, D. C.

20555 Dr. Richard F. Cole Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comnission Mashington, D.

C 20555 Dr. Emneth A. Luebke Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comnission Washington, D. C.

20555 Hr. Thomas B. Cochran Natural Resources Defense Council, Inc.

1725 I Street, N. M.

Suite 600 Washington, D. C.

20006 4

~

0728F SEP TECHNICAL EVALUATION TOPIC VIII-2 DIESEL GENERATORS R. E. Ginna Docket No. 50"244 July 1980 July 7, 1980

CONTENTS

1.0 INTRODUCTION

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

1 2 '

CRITERIA

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

2 2.1 Diesel Generator Loading 2.2 Bypass of Protective Trips 2.3 Diesel Generator Testing

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

2

~

2

~

3 3

0 DISCUSSION AND EVALUATION

~

~

~

~..

~

~

~

~

~

~

~

~

~

~

~

~

~

~ ~, 6 3.1 Diesel Generator Loading 3.2 Bypass of Protective Trips 3.3 Diesel Generator Testing

~

~

~

~

~

~

~

t

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

6

~

7

~

7 4 t 0

SUMMARY

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

9 5 ~ 0 REFERENCE S

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

9

SEP TECHNICAL EVALUATION TOPIC VIII-2 DIESEL GENERATORS R. E. Ginna

1. 0 INTRODUCTION The objective of the review is to determine if the onsite AC generator for the R. E. Ginna Nuclear Station has sufficient capacity and capability to supply the required automatic safety loads during anticipated occurrences and/or in the event of postulated accidents after loss of offsite power.

The requirement that the onsite electric power supplies have capacity and capability to complete the required safety functions is contained in General Design Criterion 17.

Criterion III> "Design Control," of Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,"

to 10 CFR Part 50 includes a requirement that measures be provided for veri-fying or checking the adequacy of design by design reviews, by the use of alternate or simplified calculational methods, or by the performance of a suitable testing program.

Regulatory Guides, IEEE Standards, and~Branch Technical-Positions which provide a basis acceptable to the NRC staff for compliance with GDC17 and Criterion III include:

Regulatory Guide 1.9> "Selection of Diesel Generator Set Capacity for Standby Power Supplies;" Regulatory Guide 1.108, "Periodic Testing of Diesel Generators Used as Onsite Power Systems at Nuclear Power Plants";

IEEE Standard 387-1977, "Criteria for Diesel-Generator Units Applied as Standby Power Supplies for Nuclear Power Stations;"

BTP ICSB2, "Diesel-Generator Reliability Qualification Testing";

and BTP ICSB17, "Diesel Generator Protective Trip Circuit Bypasses."

Specifically, this review evaluates the loading of the diesel-generator, bypasses of protective trips during accident conditions and periodic testing.

'Ihe SEP reviews for Topics III-1 and III-12 will evaluate the diesel-generator qualification.

2. 0 CRITERIA 2.1 Diesel Generator Loadin.

Regulatory Guide 1.9> "Selection of Diesel-Generator Set Capacity for Standby Power Supplies," provides the basis acceptable to the NRC staff for loading diesel"generator units.

The following criterion is used in this report to determine compliance with current licensing requirements:

(1)

The automaticallymonnected loads on each diesel-generator unit should not exceed the 2000-hour rating.

(Loads must be conservatively estimated utilizing the nameplate ratings of motors and transformers with motor efficiencies of 90X or less.

When available, actual measured loads can be used.)

2.2 B

ass of Protective Tri s.

Branch Technical Position (BTP)

ICSB 17, "Diesel-Generator Protective Trip Circuit Bypasses,"

specifies tha t:

(1)

The design of standby diesel generator systems should retain only the engine overspeed and the generator differential trips and bypass all other trips under an accident condition (2) If other trips, in addition to the engine overspeed and generator differential, are retained for accident con-

ditions, an acceptable design should provide two or more independent measurements of each of these trip parameters.

Trip logic should be such that diesel-generator trip would require specific coincident logic.

2.3 Diesel Generator Testing.

Regulatory Guide 1.108> "Periodic Tesing Of Diesel Generator Units Used as Onsite Electrical Power Systems at, Nuclear Power Plants", states that:

(1)

Testing of diesel-generator units, at least once every 18 months, should:

(a)

Demonstrate p'roper startup operation by simulating loss of all ac voltage and demonstrate that the diesel generator unit can start automatically and attain the required voltage and frequency within acceptable limits and time.

(b)

Demonstrate proper operation for design-accident-loading sequence to design-load requirements and verify that voltage and frequency are maintained within required limits.

(c)

Demonstrate full-load-carrying capability for an interval of not less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, of which 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> should be at a load equivalent to the continuous rating of the diesel generator and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at a load equivalent to the 2&our rating of the diesel generator.

Verify that voltage and frequency requirements are maintained.

'Ihe test should also verify that the cooling system func-tions within design limits.

(d)

Demonstrate proper operation during diesel-generator load shedding, including a test of the loss of the largest single load and of complete loss of load, and verify that the voltage require-ments are met and that the overspeed limits are not exceeded.

(e)

Demonstrate functional capability at full-load temperature conditions by rerunning the test phase outlined in (a) and (b), immediately following (c), above.

(f)

Demonstrate the ability to synchronize the diesel generator unit with offsite power while the unit is connected to the emergency load, transfer this load to the offsite power, isolate the diesel-generator unit, and restore it to standby status.

(g)

Demonstrate that the engine will perform properly if switching from one fuelmil supply system to another is a part of the normal operating proced-ure to satisfy the 7&ay storage requirement.

(h)

Demonstrate that the capability of the diesel-generator unit to supply emergency power within the required time is not impaired during periodic testing under (3), below.

(2)

Testing of redundant diesel~enerator units during normal plant operation should be performed indepen-dently (nonconcurrently) to minimize common failure modes resulting from undetected interdependences among diesel~enerator units.

However, during reliability demonstration of diesel-generator units during plant preoperational testing and testing subsequent to any plant modification where diesel-generator unit inter>>

dependence may have been affected or every 10 years (during a plant shutdown), whichever is the shorter, a

test should be conducted in which redundant units are started simultaneously to help identify certain common failure modes undetected in single diesel-generator unit tests.

(3) periodic testing of diesel-generator units during nor-mal plant operation should:

(a)

Demonstrate proper startup and verify that the required voltage and frequency are automatically attained within acceptable limits and time.

This test should also verify that the components of the diesel~enerator unit required for automatic startup axe operable.

(b)

Demonstrate full-load~arrying capability (contin-uous rating) for an intexval of not less than one hour.

'Ihe test should also verify that the cooling system functions within design limits.

This test could be accomplished by synchronizing the generator with the offsite power and assuming a load at the maximum practical rate.

(4)

The interval for periodic testing under (3), above (on a per diesel~enerator unit basis) should be no more than 31 days and should depend on demonstrated perfor-mance.

If more than one failure has occurred in the last 100 tests (on a per nuclear unit basis),

the test interval should be shortened in accordance with the following schedule.

(a) If the number of failuxes in the last 100 valid tests is one or zero, the test interval should be not more than 31 days.

(b) If the number of failures in the last 100 valid tests is two, the test interval should be not more than 14 days.

(c) If the number of failures in the last 100 valid tests is three, the test interval should be not more than 7 days.

(d) If the number of failures in the last 100 valid tests is four or more, the test interval should be not more than 3 days.

3.0 DISCUSSION AND EVALUATION Since both diesel generators'orst-case loads, protective trips, and trip bypasses are identical, a review of one serves as a review of both.

3.1 Diesel-Generator Loading.

Discussion.

On November 22,

1978, RGB provided a current list of loads automatically connected to the diesel generators in the event of a L'OCA concurrent with a loss of offsite power (Reference 1).

Discussion with the licensee (Reference

2) established that the KW load values listed in Table 8.2-1 of the FSAR (Reference

3) are measured

values, so it is not necessary to use the 90X motor efficiency in conversion of HP to KW.

The maximum step load change is 539 KW (28X of continuous capacity) which occurs 15 seconds after the diesel generator start signal.

Evaluation.

Ginna Technical Specifications require a test of the diesel response to an emergency start signal during each refueling outage, but do not require the generators to assume emergency loads (Reference 4).

The maximum automatically connected load to either generator is 1995 KW which occurs during the injection phase of the LOCA response.

The maximum long-term automatically connected load is 1517 KW.

'Ihe diesel generators are rated at 2300 KW for 30 minutes, 2250 KW for two hours, and 1950 KW continuous.

3herefore, the total automatically connected load (at 87X of

3.2 Bypass of Protective Trips Discussion.

On May 19,

1977, RG6E provided a list of protec-tive trips which render the diesel generators incapable of responding to an automatic emergency start signal (Reference 5)-

The protective trips which are not bypassed under emergency conditions are low lubricating oil pressure and overspeed.

The low oil pressure trip uses three sensors and two out of three logic.

Evaluation.

The only protective trips which are not bypassed under emergency conditions are overspeed and low lubricating oil pres-

sure, and the low oil pressure uses redundant sensors and coincident logic.

Therefore, the diesel generator protective trips meet the re-quirements of BTP ICSB17.

3.3 Diesel Generator Testing Discussion.

Ginna Technical Specifications, paragraph 4.6.1, require diesel~enerator testing as follows:

(1)

Manually-initiated start of the diesel generator, followed by manual synchronization with other power sources and assumption of load by the diesel generator up to the name-plate rating.

This test shall be conducted monthly on each diesel generator.

Normal plant operation will not be affected.

(2)

Automatic start of each diesel generator and automatic restoration of particular vital equipment, initiated by an actual loss of all normal AC station service power supplies together with a simulated safety injection signal.

This test shall be conducted during each refueling shutdown to assure that the diesel~enerator will start and following maximum breaker closure times after the initial starting signal for trains A and B

will not be exceeded.

A B

Diesel plus Safety Injection Pump 20 sec.

22 sec.

plus RHR Pump All breakers closed 40 sec.

42 sec.

(3)

Each diesel generator shall be given a thorough inspection at least annually following the manufacturer's recommendations for this class of standby service.

The above tests will be considered satisfactory if all applicable equipment operates as designed.

(4)

Diesel generator electric loads shall be not increased beyond the long-term rating of 1950 KV.

Evaluation.

Diesel-generator testing defined in the plant Technical Specifications address the criteria listed in paragraph 2.3 to the following extent:

(1)(a)

Voltage and frequency not specified (b)

Voltage and frequency not specified (c)

Duration not specified; load is limited to less than short-term automatically connected load (d)

Not addressed (e)

Not addressed (f)

Not addressed

(g)

Not applicable (h)

Not addressed (2)

Not addressed (3)(a)

Synchronization is manual; time limit is not specified (b)

Duration is not specified; load is limited to less than short-term automatically connected load.

(4)

Not addressed.

The Technical Specifications do not meet current licensing criteria for diesel-generator testing.

Diesel-generator failure data will be extracted by NRC from Licensee Event Reports and will be considered in the final evaluation of testing adequacy.

4.0 SUMMITRY Automatic diesel generator loading is in compliance with current licensing criteria.

'Ihe bypass of diesel generator protective trips is in agreement with current NRC staff guidelines.

Diesel-generator

testing, as specified by plant Technical Specifications, does not meet current licensing criteria.

The review of qualification of the diesel generators will be completed with SEP Topics III-l, Seismic Qualification, and III-12, Environmental Qualification.

5. 0 REFERENCE S 1.

Letter RG&G (White) to NRC (Ziemann) dated November 22, 1978.-

2.

Final Safet Anal sis Report, updated but no date given (Table 8.2-1 is dated January 1969).

3.

Telephone conversation RG&E (P. Wilkens) and EG&G Idaho, Inc.

(F. Farmer),

May 2, 1979.

4.

Technical Specifications (Chan e No.

6) for R.

ED Ginna Nuclear Power Plant Unit No. 1, paragraph 4.6.1.b. issued March 1, 1972.

5 ~

Letter RG&E (Madgett) to NRC (Schwencer) dated May 19, 1977.

6.

General Design Criterion 17, "Electric Power System," of Appendix A, "General Design Criteria of Nuclear Power Plants," to 10 CRF Part 50, "Domestic Licensing of Production and Utilization Facilities."

7.

General Design Criterion III, "Design Control," of Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CRF Part 50, "Domestic Licensing of Production and Utilization Facilities."

8.

"Standard Criteria for Class IE Power.Systems and Nuclear Power Generating Stations,"

IEEE Std.

308, 1974, paragraph 5.2.4.

9.

"Criteria for Diesel>>Generator Units Applied as Standby Power Supplies for Nuclear Power Stations,"

IEEE Std.

387, 1977.

10'Selection of Diesel Generator Set Capacity for Standby Power Supplies," Regulatory Guide 1.9.

11.

"Periodic Testing of Diesel Generators Used as Onsite Power Systems at Nuclear Plants," Regulatory Guide 1.108.

10

12.

"Diesel-Generator Reliability Qualification Testing",

BTP ICSB2 (PSB).

13.

"Diesel-Generator Protective Trip Circuit Bypasses,"

BPT ICSB17 (PSB).

11