ML18142B950
| ML18142B950 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/21/1977 |
| From: | LeBoeuf, Lamb, Leiby & MacRae, Rochester Gas & Electric Corp |
| To: | Case E Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18142B950 (20) | |
Text
U S ~ NUCLEAR REGULATORY C t
NRC,FDRM 195 I2-7B)
~
'NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL ON DOCKET NUMBER So -0M FILE NUMBER TO Mr. Edson G.
Case FROM:
- LeBoeuf, Lamb, Leiby & MacRae Washington, D.
C.
20036
- LeBoeuf, Lamb, Leiby & MacRae DATE OF DOCUMENT DATE RECEIVED I.ETTE R ABORIGINAL C3 cop v OTOR IZED RCUNC LASS IF I E D PROP INPUT FORM NUMBER OF COPIES RECEIVED DESCRIPTION ENCLOSURE License No.
DPR-18 apl For Amend:
tech specs proposed change concerning modifica-tions of requirements for diesel generator test>>
ing. ~.Notorized 11/16/77........W/Att Cert of Svco
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
1p 15P DISTRIBUTION OF MATERIAL CONCERNING ONSITE EMERGENCY POWER SYSTEMS PLANT NAIIE.
Re E, GINNA UNIT g 1 jcm 11/22/77 SAFETY BRANCH CHIEF:
FOR ACTION/INFORMATION C? Rr oPS&Btf.
REG FILE INTERNALDISTR I BUTION I G E(2)
OELD MIPC HANAUER BENAROYA IPPOLITO EISENHUT SHAO BAER BUTLER GRIMES F.
ROSA T.
WAMBACH D. TONDI D.
MCDONALD D. JAFFF, LPDR'6 CYS ACRS CATEGOR EXTERNALDISTRIBUTION C NTROL NUMBER 7732so167
LEBOEUF, LAMB,LEIBY 8L MACRAE l757 N STREET, N.W.
WAsHINGTQN, D. C. 20036 TELEPHONE 202 457 7600 LEON A. AI.LKN.JR.
JOSEPH K. BACHKLDKR.ZI CRNKST S. BALLARD.JR.
O. S PETER BCRGEN 8 OEOFFRY D. C. BEST DAVID P. DICKS TAYLOR R. BRIGOS CHARLES N. BVROER THOMAS E ~ BVRKE ROGER D.FELDMAN 4 CVGKN C R. FIDEL L i 4 JACOB FRICDLANDCR DONALD J. ORKENE JAMES A ORKERsII 4 JOHN L.GROSC 4 DOUGLAS W.HAWKS CARL D.HOBCLMAN MICHAEL IOVCNKO JAMES F JOHNSON,4' RONAI.D D. JONES LCX K.LARSON+4 ORANT S.LEWIS CAMERON F. MACRAE 2 CAMCRON F. MACRAK,IE2 GKRARD A,MAHER SHCILA H. MARSHALL JAMES G. McKLROY JAMES P. McGRANERY.JR! i PHILIP PALMER MCOUIOAN JAMCS O MALLEY,JR. i J ~ MIC H ACL PAR IS H JOHN A.RVDY PAUL O. RUSSELL HAROLD M. SKIDEI.
CHARLES P. SIFTON HALCYON O. SKINNER JOSEPH S.STRAUSS SAMUEL M.SUGDKN EUGENE B, THOMAS,JR!4 LKONARD M TROSTCN+4 HARRY H.VOIOT+2 H. RICHARD WACHTKL OERARD P. WATSON CA8LC ADORC$8 I 28WIH,WASHIHOTOH,0.0.
TELEX: 440274 RANDALLJ. Lc80EVF,JR. I929-l976 ADRIAN C, LCISY l952 l975 OF COUHSCL AHVIH C. UPTON I40 BROADWAY HEW YORK, H.Y. I0005 TKLKPHOHC 2I2 289 II00 CAQLC ADORCSS LEBWIH,HEW YORK TELEX: 42$ 4IS 4RESIDCNT PARTNERS WASHINGTON OFFICF 4 ADMITTED 'TO THK DISTRICT OF COLUMBIA BAR Mr. Edson G.
Case Acting Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory November 21, 1977l 'I2g I
\\'IUUI.'
NOW 2 U9
~>>ULAIQKT QA~~TB2$$5ION
~, F Commission Washington.
D-C.
20555 cp t
t f
Il Re:
Rochester, Ga's and Electric Corporation R. E. Ginna Nuclear Power Station, Unit, No.
1 Docket No.
50-244
Dear Mr. Case:
As counsel for Rochester Gas and Electric Corpora-
- tion, we hereby transmit three (3) signed originals and nineteen (19) copies of a document entitled, "Application for Amendment to Operating License."
This Application seeks to amend Technical Specification 4.6 set forth in Appendix A to Provisional Operating License No. DPR-18, to modify the requirements for diesel generator testing.
Forty (40) copies of this proposed change and of the safety evaluation there-for are also transmitted herewith."
A Certificate of Service showing service of the'se documents upon the persons listed therein is also enclosed.
y kadfd~
Enclosures
J I
L L1
~r
~
i, -p$
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of Rochester Gas and Electric Corporation (R.E. Ginna Nuclear Power Plant, Unit No.
1)
)
)
)
Docket No. 50-244
)
)
APPLICATION FOR AMENDMENT TO OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the U.S.
Nuclear Regulatory Commission (the "Commission" ), Rochester Gas and Electric Corporation
("RGGE"), holder of Provisional Operating License No. DPR-18, hereby requests that the Technical Specification 4.6 set forth in Appendix A to that license be amended to modify the requirements for diesel generator testing.
This request for a change in the Technical Specifications is submitted to eliminate conflicting requirements for diesel generator testing.
The proposed technical specification change is set forth in Attachment A to this Application.
A safety evaluation is set forth in Attachment B.
This evaluation also demonstrates that the proposed change does not involve a significant change in the types or a significant increase in the amounts of effluents or any change in the authorized power level of the facility.
WHEREFORE, Applicant respectfully requests that Appendix A to Provisional Operating License No. DPR-18 be amended in the form attached hereto as Attachment A.
Rochester Gas and Electric Corporation By L. D. White, Jr.
Vice President, Electric and Steam Production Subscribed and sworn to before me on this /&today of November 1977.
GARY L. REISS NOTARY PUBLlC, State o5 N. Y. Monroe Co.
My Cornrnission Expires March 30, 19......
BEFORE THE UNXTED STATES NUCLEAR REGULATORY COMMXSSION
)
)
ROCHESTER GAS AND ELECTRXC
)
CORPORATION
)
(R. E. Ginna Nuclear Power
)
- Station, Unit, No. 1)
)
Docket No. 50-244 CERTIFICATE OF SERVXCE I hereby certify that I have served a document entitled, "Application for Amendment to Operating License" together with a copy of the proposed changes to Technical Specifications and the safety evaluation therefor by mailing copies thereof first class, postage prepaid to each of the following persons this 21st day of November, 1977:
- Chairman, Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Atomic Safety and Licensing Appeal Board U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Mr. Michael L. Slade 1250 Crown Point Drive
- Webster, New York'4580 Warren B. Rosenbaum, Esq.
One Main Street East 707 Wilder Building Rochester, New York 14614 L.
Dow Davis, IV, Esq.
Office of the Executive Legal Director U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Edward Luton, Esq.
Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Dr.
Emmeth A. Luebke Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D. C.
20555
Dr. A. Dixon Callihan Union Carbide, Corporation P.'.
Box Y Oak Ridge, Tennessee 37830 Mr. Robert N. Pinkney Supervisor Town of Ontario 107 Ridge Road Nest
- Ontario, New York 14 519 Jeffrey L. Cohen, Esp.
New York State Energy Office Swan Street Building Core I, Second Floor Empire State Plaza
- Albany, New York 12223 Arthur M. Schwartzst in
- LeBoeuf, Lamb, Leiby 6 MacRae Attorneys for Rochester Gas and Electric Corporation
ATTACHMENT A 1.
Replace Technical Specification pages 4.6-1 and 4.6-2 with the revised pages 4'-1, 4.6-1a and 4.6-2.
We EP
~
'qa
4.6 Emer enc Power S stem Periodic Tests A licabilit Applies to periodic testing and s'urveillance requirements of the emergency power system.
~Ob ective To verify that the emergency power system will respond promptly and properly when required.
The following tests and surveillance shall be performed as stated:
4.6.1 Diesel Generators Each diesel generator shall be demonstrated operable:
a ~
Except during cold or refueling shutdown at least once per 31 days by:
1.
Verifying the fuel level in the.day tank, 2.
Verifying a minimum oil storage of 10,000 gallons is at the
- station, 3.
Verifying the fuel transfer pump can be started and transfer fuel from the storage system to the day tank, 4.
Verifying the diesel starts from normal standby conditions, 5.
Verifying the generator is synchronized, loaded to at least 1950 kw but less than the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> rating of 2250 kw and operates for at least 60 minutes but less than 120 minutes, 6.
Verifying the diesel generator is aligned to provide standby power to the associated emergency buses.
b.
The tests in specification 4.6.la will be performed prior to C ~
exceeding 5% power if the time since the last test exceeds 31 days.
At least once per 92 days by veri'fying that a sample of diesel water and sediment, viscosity, SSU at 100oF 4.6-1 Proposed fuel from the fuel storage tank is within the following limits:
0.10 volume percent 32 to 45
II,
~
Tg el i;
I P
~
d.
At least once per 18 months dur'ing shutdown by:
1.
Inspecting the diesel in accordance with the manufacturer's recommendations for this class of standby service, 2.
Verifying the generator capability to reject a load of 295 KW without tripping, 3.
Simulating a loss of offsite power in conjunction with a safety injection test signal and:
(a)
Verifying de-energization of the emergency buses and load shedding from the emergency buses.
(b)
Verifying the diesel starts from normal standby condition on the auto-start signal, energizes the emergency buses with permanently connected
- loads, energizes the automatically conneoted emergency loads with the following maximum breaker closure times after the initial starting signal
'or trains A and B not being exceeded A
B Diesel plus Safety Injection Pump 20 sec 22 sec plus RHR Pump All breakers 40 sec 42 sec and operates for >~ five minutes while its generator is loaded with emergency loads.
(c) Verifying that all diesel generator trips, except engine overspeed, low lube oil pressure, and overcrank, are automatically bypassed upon loss of voltage on the emergency bus and/or safety injection actuation signal.
4;6-la Proposed
0 C
4.6.2 Station Batteries a.
Every month the voltage of each cell (to the nearest 0.01 volt),
the specific gravity and temperature of a pilot cell in each battery shall be measured and recorded.
I b.
Every 3 months the, specific gravity of each cell, the tempera-ture reading of every fifth cell, the height of electrolyte, and the amount of water added shall be measured and recorded.
4.6-2 Proposed
S
~ '
~
9 X
0 t I
E
.Attachment B
Technical Specification 4.6.1, diesel generator testing, now requires that the diesel generator
'.be loaded to its nameplate rating (4.6.1.a) and that the electrical loads on the diesel generator not be increased beyond the long term rating of 1950kw (4.6.1.d).
The generator nameplate 'specifies 2500kVa and 80% power factor.
To remedy the inconsistency, the testing requirements for the diesel generator have been revised.
In addition,'testing requirements have been expanded to include other components important to diesel generator operability.
The Standard Technical Specifications published by the NRC have been used as guidance in preparation of the proposed Technical Specifications.
Operability of the diesel generators is assured by periodic
.testing on a 31 day interval.
This includes assuring that at least 10,000 gallons of fuel oil are on site, as specified in FSAR Section 8.2.3 and checking the fuel oil level in the day fuel tank.
Since the day tank provides fuel for approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of diesel operation, the entire balance of the 10,000 gallon onsite supply need not be automatically available to each diesel.
Operator action is acceptable to provide this fuel to the diesel.
The fuel transfer pumps are tested.
The diesel generator is loaded for at least 60 minutes to at least its continuous rating of 1950kw but not beyond its 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> rating of 2250kw.
Finally, the diesel generator is aligned to provide standby power to associated emergency busses.
By performing these tests, assurance is provided that, if required, the diesel generators would start,
.accept load, and operate as assumed in the safety analyses.
The fuel oil is demonstrated to meet the manufacturer's recommended limits for viscosity, water and sediment at least once every 92 days.
This will provide assurance of the acceptability of the diesel fuel.
At least once every 18 months, comprehensive testing will be performed during a shutdown.
This includes testing that cannot be performed during normal plant operation.
As in the present Technical Specifications, the diesel is inspected in accordance with the manu-facturer's instructions.
Verification is obtained that the largest single emergency
- load, 295kw, can be rejected without tripping the diesel generator.
The value of 295kw is based upon the 350 horse-power motor for a safety injection pump (see FSAR Table 8.2-1).
The specifications would continue to require testing the diesel generator by simulating a loss of offsite power in conjunction with a safety.
injection signal.
Breaker closure times for loads are recorded and are required to meet acceptance criteria as established in the safety analyses.
I V
e
~ '
Each safeguards load which is automatically sequenced onto the diesel generator has its own individual timer which controls its loading.
Because verification of the operability of the timer would require taking the entire train out of service or starting the entire train and because testing at refueling intervals in the past has not. disclosed unacceptable drift in the timer setpoints, it is proposed that timer testing be performed at refueling outages.
In addition, testing is performed to assure that generator trips are properly set.
A more complete description og diesel generator trips may be found in Supplement 1 to Technical Supplement AcCoppanying Application for a Pull-Term Operating License, December 20; 1973'.
(response to question
- 9).
The Ginna design does not provide for full flow verification to demonstrate the magnitude of the automatically connected loads under simulated accident conditions.
Pump's are supplied with small recirculation lines rather than full flow test. loops.
- Thus, con-firmatioq of acceptability'of diesel generator loadings has been provided through analyses.
These analyses are summarized in Section 8.2.3 of the FSAR and in the discussion of Safety Guide 9 in the Technical Supplement Accompanying Application for a Full-Term Operating License.
By performing the proposed tests, assurance will be provided that the diesel generators will perform their required safety function if required.
E