ML19343A597
| ML19343A597 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/15/1980 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| TASK-08-02, TASK-8-2, TASK-RR NUDOCS 8011190073 | |
| Download: ML19343A597 (14) | |
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[ pen UNITED STATES o,,
NUCLEAR REGULATORY COMMISSION 2
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.I WASHINGTON, D. C. 20555
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Septeder 15, 1980 Q
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Docket No. 50-219 E,ii l$
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Jersey Central Power & Light Company Madison Avenue at Punch Bowl Road l
Morristown, New Jersey 07960 j
Dear Mr. Finfrock:
RE: SEP TOPIC VIII-2 ONSITE EMERGENCY PO'..'ER SYSTEMS (Oyster Creek)
Enclosed is a copy of our evaluation of Systematic Evaluation Program Topic VIII-2, Onsite Emergnecy Power Systems.
This assessment compares your facility, as described in Docket No. 50-219, 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 within 45 days of receipt of this letter.
This evaluation will be a basic input to the intecrated safety assessment for your facility unless you identify changes needed to reflect the as-built conditions at your f acility.
This topic assessment may be revised in the future if your facility design is changed or if NRC criteria relating to this topic is modified before the integrated assessment is completed.
Sircerely, 711 JJ Dennis M. Crutchfield, def Operating Reactors Branch #5 Division of Licensing
Enclosure:
Cocpleted SEP 2
Topic VIII-2 cc w/ enclosure:
See next page NO W3 h lD @ M D
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8821288 0 7 3
i 2-Septemb er 15, 1980 Mr. I. R. Finf rock, Jr.
u CC G. F. Trowbridge, Esquire Gene Fisher Shaw, Pittman, Potts and Trowbridge Bureau Chief 1800 M Street, N. W.
Bureau of Radiation Protection Washington, D. C.
20036 380 Scotts Road
- j Trenton, New Jersey 08628 GPU Service Corporation ATTN: Mr. E. G. Wallace Comissioner Licensing Manager New Jersey Department of Energy
- f 260 Cherry Hill Road 101 Commerce Street l
Parsippany, New Jersey 07.154 Newark, New Jersey 07102 Natural Resources Defense Council Plant Superintendent 91715th Street, N. W.
Oyster Creek Nuclear Generating
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Washington, D. C.
20006 Stption
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P. O. Box 388 Forked River, New Jersey 08731 Steven P. Russo, Esquire 248 Washington Street Resident Inspector 3
P. D. Box 1060 c/o U. S. NRC iems River, New Jersey 087S3 P. O. Box 128 Forked River, New Jersey 08731 Joseph W. Ferraro, Jr., Esquire Deputy Attorney General Director, Technical Assessment Div.
State of New Jersey Office of Radiation Programs Department of Law and Public Safety (AW-459) 1100 Raymond Boulevard U. S. Environmental Protection Newark, New Jersey 07012 Agency Crystal Mall #2 e.n County Library Arlington, Virginia 20460 drick Township Branch 401 Chambers Bridge Road U. S. Environmental Protection l
Brick Town, New Jersey 08723 Agency Region II Office Mayor ATTN: EIS C0ORDINATOR Lacey Township 26 Federal Plaza P. O. Box 475 New York, New York 10007 Forked River, New Jersey 08731 Comn, sioner Department of Public Utilities State of New Jersey 101 Comerce Street Newark, New Jersey 07102 l
0713F SEP IECliNICAL E'IALUATION TOPIC VIII-2 DIESEL GENERATORS OYSTER CREEK Docke t No. 50-219 June 1980 June 24, 1980 t
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CONTENTS 1
1.0 INTRODUCTION
2 2.0 CRITERIA.
2 2.1 Dies el Generator Loading 2
2.2 Bypass of Protective Trips 3
2.3 Diesel Generator Testing 6
3.0 DISCUSSION AND EVALUATION 6
3.1 Diesel Generator Loading 7
3.2 Eypass of Protective Trips 7
3.3 Diesel Generator Testing 9
4.0
SUMMARY
9 5.0 PT.FERENCES.
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SEP TECHNICAL EVALUATION TOPIC VIII-2 DIESEL GENERATORS OYSTER CREEK
1.0 INTRODUCTION
The objective of the review is to determine if the onsite AC generator for the Oyster Creek 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 af ter 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 Des ign Criterion 17.
Criterion III, " Design Control," of Appendia 3, " 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 al ternate or simplified calculational methods, er by the performance of a
.ble testing program.
Regula tory Guide s, 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;" Fegulatory Guide 1.108,
" Periodic Testing of Diesel Generators Used as Onsite Power Systems at Nuclear Powe r Plants"; IEEE Standard 387-1977, " Criteria for Diesel-Generator Units Applied as Standby Power Supplips for Nuclear Power Stations;" BTP ICSB2, " Diesel-Cenerator Reliability Qualification Testing";
and BTP ICSB17, " Diesel Generator Protective Trip Circuit Bypasses."
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Specifically, this review evaluates the loading of the diesel-generater, bypasses of protective trips during accident conditions and periodic testing.
The SEP reviews for Topics III-1 and III-12 will evaluate the diesel-generator qualification.
2.0 CRITERIA 2.1 Diesel Generator Loading. Regulatory Guide 1.9, " Selection of Diesel-Generator Set Capacity for Standby Power Supplies," provides the basis acceptable to the NRC staf f for loading diesel-generator units.
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following criterion is used in this report to determine compliance with current licensing requirements:
(1) The automatically-connected 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 90% or less. When available, actual measured loads can be used.)
2.2 Bypas s o f Protective Trips.
Branch Technical Position (BTP) 17, " Diesel-Generator Protective Trip Circuit Sypasses," specifies I
.aaL:
(1)
The design of standby diesel generator systems should retain only the engine overspeed and the generator dif ferential trips and bypass all other trips under an accident condition (2)
If other trips, in addition to the engine overspeed and generator dif ferential, 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 coincidaa t lo g ic,
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2.3 Diesel Generator Testing.
Regulatory Guide 1.108, " Periodic i
Testing Of Diesel Generator Units Used as Onsite Electrical Power Systems at Nuclear Power Plants", states thats.
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(1) Testing of diesel-generator units, at 1 cast :r:>e every j
18 months, should:
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i (a) Demonstrate proper startup operation by simulating loss of all ac voltage and demonstrate that the diesel generatcr unit can start automatically and a
j attain the required voltage and frequency within i
acceptable. limits and time.
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(b) Demonstrate proper operation for design-accident-i loading sequence to design-load requirements and verify that voltage and frequency are maintained i
within required limits.
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(c) Demonstrate full-load-carrying capability for an 1
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 i
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-hour racing of the diesel generator. Verify that voltage and frequency requirements are maintained.
The test
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should also verify that the cooling system func-tions within design limits.
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(d) Demonstrate proper operation during diesel-generator _ load shedding, including a test of the i
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.
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(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 of fsite power while the unit is connected to the emergency load, transfer this load to the of fsite power, isolate the diesel-generator unit, and restore it to standby status.
(g) Demonstrate that the engine will perform properly if switching from one fuel-oil supply system to another is a part of the normal operating proced-ure to satisfy the 7-day 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 generator units during normal plant operation should be performed indepen-dently (nonconcurrently) to minimize common failure modes resulting from undetected interdependences among diesel-generator 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 af fected 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.
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1 (3) Periodic testing of diesel-generator units during nor-mal plant operation should:
4 (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 i -
diesel-generator unit required for automatic i.
startup are operable.
i (b) Demonstrate full-load-carrying capability (contin-uous rating) for an interval of not less than one j.
hour. The test should also verify that the i
cooling system functions within design limits.
This test could be accomplished by synchronizing the generator with the offsite power and assuming i
- a. load at the maximum practical rate.
J (4) The interval for periodic testing under (3), above (on j
1 a per diesel-generator unit basis) should be no more than 31 days and should depend on demonstrated perfor-j If more than one failure has occurred in the mance.
L last 100 tests (on a per nuclear unit basis), the test interval should be shortened in accordance with the 1
following schedule:
(a)
If the number of failures in the last 100 valid tests is one or zero, the test interval should be l
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.
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4 (c)
If the number of failures in the last 100 valid tests is three, the test interval should be not i
more than 7 days.
l (d)
If the number of failures in the last 100 valid tests is four or more, the test interval should be j
r not more than 3 days.
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f 3.0 DISCUSSION AND EVALUATION t
1 Since both diesel generator's worst-case loads, protective trips, and 1
I trip bypasses are identical, a review of one serves as a review of both.
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1 3.1 Diesel-Generator Loading Discussion.
On January 23, 1979, JCP&L provided a list of loads automatically connected to ths diesel generators in the event of a LOCA concurrent with a loss of offsite power.I Further discussion with the I
licensee corrected two typo-graphical errors in data entries, determined 2
se unstated assumption, and verified that the " Rated Condition" entries i
,.n fact, measured values for large motors. The worst-case load on a
.tiesel generator occurs in the event of a LOCA concurrent with a loss of of f site power and failure of the other diesel generator.
The maximum step load change is 748 KW (30% of capacity) which occurs when the generator is initially loaded.
Evaluation.
Oys ter Creek Technical Specifications require testing of load sequencing timers, but not of the capability of the generators to actually assume emergency loads during each refueling outage.3 The maximum automatically connected load to either generator is i
2,504 KW.
The diesel generators are raced at 2,500 KW. base load, 2,750 Ku continuous. peak load, and 3,025 KW overload capacity for two hours in any f
24-hour period. Therefore, the total automatically connected diesel l
generator load (at 91% of continuous capacity) is within the criteria I
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t 3.2 Sypass of protective Trips 4
4 Discussion.
On June 9,1977, JCP6L provided a list of pro-f tective trips which render the diesel generators incapable of reponding to an automatic emergency start signal.' The protective trips which are not i
bypassed are phase sequence voltage, undervoltage, leading VARs, reverse -
overspeed, and differential.
None of them have redundant parameter sensors and coincident logic.2 r
Evaluation. The diesel generator phase sequence voltage, undervoltage, and leading VARs protective trips are neither bypassed during accident conditions nor provided with multiple parameter sensors and j
coincident lo gic. Therefore, the use of these diesel generator protective crips during accident conditions is not in agreement with current NRC staff guidelines as listed in BTP ICSB 17.
i 3.3 Diesel Generator Testing
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I Discussion.
Oyster Creek Technical Specifications, j
paragraph 4.7.A, require diesel-generator testing as follows:
I (1)
Each diesel generator shall be started and loaded to not less than 20% rated power every two weeks.
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(2) The two diesel generators shall be automatically i
actuated and functionally tested during each V
refueling outage.
This shall include testing of the diesel generator load sequence timers listed in Table 3.1.1.
(3) Each diesel generator shall be given a thorough in spection at least annually.
(4) The diesel generators' fuel supply shall be checked following the above tests.
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(5) The diesel generators' starting batteries shall be tested and monitory 3 the same as the station batteries, Specification 4.7.B.
Evaluation.
Diesel-generator testing defined in the plant Tech-nical Specifications r?. dress the criteria listed in paragraph 2.3 to the following excent:
l (1)
(a)
No limits are specified for voltage, frequency, or time 1
(b)
No limits are specified for voltage or frequency; actual loading of generator not required (c) No limits are specified for voltage, frequency, or duration (d)
Not addressed (e)
Not addressed (f)
Not addressed l
(g) Not addressed (h)
Not addressed (2)
Not addressed (3)
(a)
No limits specified for voltage, frequency, or time; automatic-start components are not addressed (b) Load is specified as not less than 20%; duration is not specified.
(4) Test interval is two weeks; variable interval is not addressed.
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The Technical Specifications do not meet current licensing criteria for diesel-generator testing.
Diesel-generscor failure data will be extracted by NRC from Licensee Event Reports and will be considered in the final evaluation of testing adequacy.
4.0
SUMMARY
Automatic diesel generator loading is in compliance with current licensing criteria. The bypass of diesel generator protective trips is not in agreement with current NRC staf f 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-1, Seismic Qualification, and III-12, Environmental Qualification.
5.0 REFERENCES
1.
Letter JCP&L to NRC, dated January 23, 1979.
telephone conversation, JCP&L (S. Me-chant) and EG&G Idaho, In c.
(F. Farmer), April 26, 1979.
3.
Technical Specifications and Bases for the Oyster Creek Nuclear Power Plant, paragraph 4.7.A.2.
4.
Letter JCP&L to NRC, dated June 9. 1977.
5.
General Design Criterion 17, " Electric Power System," of Appen-dix A,
" General Design Criteria of Nuclear Power Plants," to 10 CFR Part 50,
'" Domes tic Licensing o f Production and Utilization Facilities."
6.
General Design Criterion III, " Design Control," 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."
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" Standard Criteria for Class IE Power Systems and !.% clear Power Generating Stations," IEEE Std. 308, 1974, paragraph 5.2.4.
8.
" Criteria for Diesel-Generator Units Applied as Standby Power Supplies
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l for Nuclear Power Stations," IEEE Std. 387, 1977.
9.
" Selection of Diesel Generator Set Capacity for Standby Power l
Supplies," Regulatory Guide 1.9.
10.
" Periodic Testing of Diesel Generators Used as Onsite Power Systems at Nuclear Plant," Regulatory Guide 1.108,
- 11. " Diesel-Generator Reliability Qualification Testing," BTP ICSB2 (PSB).
12.
" Diesel Generator Protective Trip Circuit Bypasses," BPT ICSB17 (PSB).
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