ML18142B948
| ML18142B948 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/22/1977 |
| From: | LeBoeuf, Lamb, Leiby & MacRae, Rochester Gas & Electric Corp |
| To: | Case E Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18142B948 (24) | |
Text
DISTRIBUTION AFTER ISSUANCE OF OP TING LICENSE
~NRC EORM 195 I2 7BI U.S. NUCI.EAR REGULATORYCOMMISS, OOCKET NUMBER NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL PILE NUMBER TO:
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ORIGINAL Cicor v OGSCRIPTION CINOTOR IZEO KKINCLASSIFIEO Mri Edson Gi Case PROP INPUT FORM ENCLOSURE FROM:
- LeBoeuf, Lamb. Leiby & MacRae Washington~
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- LeBoeuf, Lamb. Leiby & MacRae OATE OF OOCUMENT 12/22/77 OATS RECEIVEO 12/27/77 NUMBER OF COPIES RECEIVEO License No+ DPR-18 Appl for Amend: tech specs proposed change concerning addition of requirements for undervo1tage requirements
~ inotorized 12/16/77 '/att Certificate of Serviceo
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rr . RONALD D. JONES LEX K. LARSONS 4 ORANT S. LEWIS CAMERON F. MAcRAC 4 CAMERON F. M*cRACrDI 4 GKRARD A.MAHER SHEILA H. MARSHALL JAMES G. McKLROY JAMES P McORANCRY,JR44 PHILIP PALMCR McOUIGAN JAMCS O'MALLCY,JR.4 J ~ MICHAEL PAR19H JOHN A. RUDY PAUL G. RV99ELL HAROLD M. SKIDCL CHARLES P. SIFTOH HALCYON O. SKINNER JOSCPH S STRAUSS SAMUKI. M.SUODEN EUGENC B. THOMASrJR 44 LEONARD M.TROSTENr4 HARRY H. VOIOTr 4 H. RICHARD WACHTKL OCRARO P. WAT9ON LEBOEUFI LAMBILEIBY 84 MACRAE l757 N STREET, N.W. WASHINGTON,D. C. 20036 TELCPHOHC 202 497 7500 CASLC ADDRESS LCSWIHr WASHI 0(r'PJ TELEX 4%274 d.'~ gg~ @4rrj4rr'rrrrc 'o '. RAHDALLJ. LCSOCUFr JR. I929 I978 ADRIAH C. LCISY I952 I979 OF COVHSCL r ARVIN C. UPTON l40 BROADWAY HCW YORK, H.Y. I000$ TCLCPHOHC 2I2 209 II00 CASLC ADDRESS LCSWIHr HEW YORK TCLCX: 4234IS 4 RCSIDENT PARTNERS WASHINGTON OFFICE 4 ADMITTED TO THC DISTRICT OF COLUMBIA BAR December 22, l977 Mr. Edson G. Case Acting Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Re: Rochester Gas 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 Corporation, we hereby transmit three (3) signed originals and nineteen (l9) copies of a document entitled, "Application for Amend-ment to Operating License," together with forty (40) copies of proposed changes to Technical Specifications and accompany-ing safety evaluation.
Thi's Application seeks to amend the Technical Specifications to add requirements for under-voltage protection.
A Certificate of Service showing service of these documents upon the persons listed therein is also enclosed.
Very truly yours, WTE/bg Enclosures
III
BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of
)
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ROCHESTER GAS AND ELECTRIC,
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CORPORATION
)
(R.
E. Ginna Nuclear Power
)
Station, Unit No. '1)
)
Docket No. '50-244 CERTIFICATE OF SERVICE The undersigned hereby certifies that the "Application for Amendment to Operating License" together with a copy of the proposed changes to Technical Specifications and accom-panying safety evaluation were this twenty-second day of
- December, 1977,
- served, by first class mail, postage
- prepaid, on the following persons:
- Chairman, Atomic Safety and Licensing Board Panel 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 14580 Warren B. Rosenbaum, Esquire One Main Street East 707 Wilder Building Rochester, New York 14614 L.
Dow Davis, IV, Esquire Office of the Executive Legal Director U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Edward Luton, Esquire 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
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Dr. A. Dixon Callihan Union Carbide Corporation P.
O. Box Y Oak Ridge, Tennessee 37830 Mr. Robert N. Pinkney Supervisor Town of Ontario 107 Ridge Road West
- Ontario, New York 14519 Jeffrey L. Cohen, Esquire
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New York State Energy Office Swan Street Building Core I, Second Floor Empire State Plaza
- Albany, New York 12223 h
Walter T. Eccard
- LeBoeuf, Lamb, Leiby 6 MacRae Attorneys for Rochester Gas and Electric Corporation
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)
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)
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Docket No.
50-244
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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
("RGSE"), holder of Provisional Operating License No.
DPR-18, hereby requests that the Technical Specifications set forth in Appendix A to that License be amended to add require-ments for undervoltage protection.
This request for a change in the Technical Specifications is submitted in accordance.with a letter from A. Schwencer, Chief, Operating Reactors Branch 51, dated June 3,
1977.
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.
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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 (Q day of December 1977.
STC: II CN K
trIDA IIOTARY PUBLIC, State of II.Y, Itonrce County gy Commission Expires Inarch 30, 197+
Attachment A
1.
Remove pages 2.3-4, 2.3-8, 3.5-4, 3;5-4a, and 4.1-7.
2.
Insert the enclosed revised pages 2.3-4, 2.3-8, 2.3-9, 3.5-4a, and 4.1-7.
f.
Low reactor coolant flow >
90% of normal indicated flow.
g.
Low reactor coolant pump frequency
> 57.5 Hz.
2.3.1.3 Other reactor t'ri s a.
High pressurizer water level 92% of span b.
Low-low steam generator water level 5% of narrow range instrument span 2.3.2 Protective instrumentation settings for reactor trip interlocks shall be as follows:
2.3.2.1 Remove bypass of "at power" reactor trips at high power (low pressurizer pressure and low reactor coolant flow) for both loops:
Power range nuclear flux -'
8.5% of rated power (1)
(Note:
During cold rod drop tests, the r
pressurizer high level trip may be bypassed.)
2.3.2.2 Remove bypass of single loss of flow trip at high power:
2.3.3 Power range nuclear flux -'
50% of rated power Relay settings for 480 volt safeguards bus protection shall be as follows:
2.3.3.1 Loss of voltage relay operating time' 8.5 seconds for 480 volt safeguards bus voltages 368 volts 2.3.3.2 Degraded voltage relay operating times and setpoints, for 480 volt safeguards bus voltages 414 volts and 368 volts.
See Figure 2.3-1.
Basis:
The high flux reactor trip (low set point) provides redundant protection in the power range for a power excursion beginning from low power.
This trip value was used in the safety analysis.
2.3-4 PROPOSED
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the minimum DNB ratio increases at lower flow because the maximum enthalpy rise does not increase.
For this reason the single pump loss of flow trip can be bypassed below 50%
power.
The loss of voltage and degraded voltage trips ensure opera-bility of safeguards equipment during a postulated design basis event concurrent with a degraded bus voltage condition. (9)
(10)
References:
(1)
FSAR 14.1.1 (2)
- FSAR, Page 14-3 (3)
FSAR 14.3.1 (4)
FSAR 14.1.2 (5)
FSAR 7.2, 7.3 (6)
FSAR'.2.1 (7)
FSAR 14.1.6 (8)
FSAR 14.1.9 (9)
Letter from L.D. White, Jr. to A. Schwencer, NRC, dated July 21, 1977 (10) Letter from L.D. White, Jr. to A. Schwencer, NRC, dated September 30, 1977 2.3-8 PROPOSED
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40 00I Ul "8
E' e4 l5 S4I 0
l5 8C 8
l5 0
8 l5 8Q 1600 1400 1200 1000 800 600 400 200 pearaded Voltage Protection Figure 2. 3-1
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I (Allowable Rela 0 crating s
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Secondary Volts (120 Volts)
Primary Volts (480 Volts) 240 Percent Volts (460 Volt Base) 52%
70 80 90 92 320 368 70%
80%
103. 5.
414 90%
120 480 104%
Safeguards Bus Voltage 2.3-9
- 17. Circulating Water Flood Protection a.Screenhouse b.Condenser Page 3 of 3
1 2
3 4
5 6
NO. of MIN.
MIN.
~ PERMISSIBLE OPERATOR ACTION NO. of CHANNELS OPERABLE DEGREE OF BYPASS IF CONDITIONS OF CHANNELS TO TRIP CHANNELS REDUNDANCY CONDITIONS COLUMN 3 or 5
CANNOT BE MET Power operation may be con-tinued for a period of up to 7 days with 1 channel in-operable or for a period ~
24 hrs. with two channels-~
Power operation may be con-tinued for a period of up to 7 days with 1 channel in-operable or for a period of 24 hrs. with two channels inoperable.
18.
Loss of Voltage 480 Volt Safe-2/bus 1/bus 1/bus guards Bus 19-Degraded Voltage 480 Volt Safe-2/bus 1/bus 1/bus guards Bus NOTE 1:
When block condition exists, maintain normal operation.
Maintain hot shutdown or place bus on diesel generator Maintain hot shutdown or place bus on diesel generator F.P.
=
Full Power Not Applicable
- If both rod misalignment monitors (a and b) are inoperable for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or more, the nuclear overpower trip shall be reset to 93% of rated power in addition to the increased surveillance noted.
- If a functional unit is operating with the minimum operable
- channels, the number of channels to trip the reactor will be column 3 less column 4.
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A channel is considered operable with 1 out of 2 logic or 2 out of 3 logic.
PROPOSED
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Channel TABLE 4.1-1 (CONTINUED Check Calibrate Test Remarks 25.
Containment Pressure M
Narrow range containment pressure
(-3.0,
+3 psig excluded) 26.
Steam Generator Pressure 27.
Turbine First Stage Pressure-28.
Emergency Plan Radiation Instruments 29.
Environmental Monitors N.A.
N.'A.
30.
Loss of Voltage 480 Volt Bus N.A.
31.
Degraded Voltage 400 Volt Safeguards Bus N.A.
D B/N Each Shift Daily Biweekly Quarterly M
Monthly P
Prior to each startup if not done previous week Each Refueling Shutdown N.A.
Not applicable PROPOSED
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Attachment B
By letter dated June 3,
- 1977, the NRC requested that RG&E assess the susceptibility of safety related electrical equipment with regard to (1) sustained degraded voltage conditions at the offsite power sources and (2) interaction between the offsite and onsite emergency power sources.
An analysis of undervoltage protection at Ginna Station was performed and submitted to the NRC in a letter dated July 21, 1977.
This analysis reviewed the current undervoltage protection and described a modification which would reduce the Station's su cep-tibilityto a sustained degraded voltage.
The basis for the modification was described;
- however, due to lack of specific in-formation regarding certain equipment, specific setpoints for the additional undervoltage protection could not be established.
Following receipt of additional information, RGsE submitted suggested setpoints in a letter to the NRC dated September 30, 1977.
The proposed specifications are identical to those pre-sented in the September 30 letter.
The proposed Specifications will provide protection both for complete loss of 480 volt bus voltage and for degraded bus voltage.
The loss of voltage protection, provided by existing equipment, will assure that assumptions of all safety analyses are met for a complete loss of voltage to safeguards equipment.
Specifically, equipment will be loaded onto the diesel generators within the time assumed in the safety analyses.
The undervoltage relay
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protection, which was identified as "second-level protection" in the June 3
NRC letter and in our two subsequent
- letters, will protect equipment against a bus voltage which is greater than the loss of voltage relay setpoint but less than the voltage guaranteed by equipment manufacturers for continuous duty for Ginna safeguards equipment.
The proposed undervoltage setpoints will provide the required protection while also assuring that spurious trips will-not occur while equipment is being sequenced onto the diesel generators.
Loss of voltage and degrade voltage conditions simulated during the refueling shutdown are performed to verify both system per-formance and relay calibration.
The safeguards 480 volt loss of voltage and degraded voltage protection systems are not part of the reactor protection system.
It is not practical to simulate these conditions during plant operation to satisfy a monthly test requirement.
Based on the analyses provided in our letters of July 21, 1977 and September 30,
- 1977, the proposed Technical Specification will provide protection against 480 volt bus undervoltage.
As stated in our letter of July 21,
- 1977, we expect that, following receipt of approval of the modification design by the NRC, detailed engineering and procurement of equipment will re-quire approximately 9 months.
Installation must be performed at a cold or refueling shutdown and would require approximately two weeks.
The effective date of a Technical Specification should be set consistent with this schedule.
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