ML17258B039
| ML17258B039 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/06/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17258B040 | List: |
| References | |
| NUDOCS 8105150362 | |
| Download: ML17258B039 (11) | |
Text
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 tri s 2.3.2 a.
High pressurizer water level -
92% of span b.
Low-low steam generator water level 5% of narrow range instrument span 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 (lofti 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 pressurizer, high level trip may be bypassed.)
2.3.2.2 Remove bypass of single loss of flow trip at high 2.3.3~
power:
Power range nuclear flux -
50% rated power Relay operating will be tested to insure that they perform according to their design characteristics which must fall in within the ranges defined below 2.3.3. 1" Loss of voltage relay operating time
< 8. 5 seconds for 480 volt safeguards bus voltages
< 368 volts.
Measured values shall fall at least 5%
limit.
This 5% margin is shown as the curve in Figure 2.3-1.
below the theoretical C
5% tolerance
- Effective 30 days after completion 2.3-4 of necessary modifications and no later than completion of the Spring 1982 refueling outage.
Amendment No.
38 (Correction - Hay l981)
2.3, 3. 2*
Basis:
Acceptable degraded voltage relay operating times and setpoints, for 480 volt safeguards bus voltages
< 414 volts and
> 368 volts are defined by the safeguard equipment thermal capability curve shown in Figure 2.3-1.
Measured values shall fall at least 5% below the theoretical limit.
This 5% margin is shown as the 5% tolerance curve in Figure 2.3-1.
The high flux. reactor trip (low set point) provides redundant protection in the power range for a power excursion beginning
~
(1) from low power.
This trip value was used in the safety analysis.
Zn the power range of operation, the overpower nuclear flux reactor trip protects the reactor core against reactivity excursions which are too rapid to be protected by temperature and pressure protective circuitry.
The overpower limit criteria is that core power be prevented from reaching a value at which fuel pellet centerline melting would occur.
The reactor is prevented from reaching the overpower limit condition by action of the nuclear overpower and overpower AT trips.
The high and low pres.ure reactor trips limit the pressure range in wh-'ch reactor operation is permitted.
The high pressurizer pressure reactor trip is also a backup to the pressurizer code safety valves for ov'erpress'ure I'rotection, and is therefore set lower than the set pressure for these valves (2485 psig).
The low pressurizer pressure reactor'rip also trips the reactor in the unlikely event of a loss of coolant accident.
- Effective 30 days after comp'letion of necessary modifications and no later than comp1etion.of the Spring 1982 refue1ing outage 2.3-5 Amendment No. 38 (Correction - May 1981)
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 operability of safeguards equipment during a postulated design basis event concurrent with a degraded bus voltage condition. (9)(10)(11)
The undervoltage set points have been selected so that, safeguards motors will start and accelerate the driven loads (pumps) within
'he required time and will be able to perform for long periods of time at degraded conditions above the trip set points without significan loss of design life; All control circuitry or safety related control centers and load centers, except for motor control center's M and L, are d.c.
Therefore, degraded grid voltages do not affect these control centers and load centers.
Motor control centers M and L, which supply the Standby Auxiliary Feedwater
- System, are fully protected by the undervoltage set points.
- Further, the Standby System is normally not in service and is manually operated only in total loss of feedwater and auxiliary feedwater.
The 5% tolerance curve in Figure 2.3-1 and the requirements of specifications 2.3.3.1 and 2.3.3.2 include 5% allowance for measurement error.
Thus, providing the measurement error is less than 5%,
measured values may be directly compared to the curve.
If measurement, error exceeds 5%, appropriate allowance shall be made.
- Effective 30 days after completion. of necessary modifications and no later than completion of the Spring 1982 refuel ing outage.
2.3-8 Amendment No. 38 (Correction - May 1981)
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LCSS AND SECOND LEVEL (D.'G.:-.-ED)*
'UXDFR VOLTAGE RELAY OP. F ~TI~'G P'-.NGES FIG. 2. 3-1 I
.l IO I
I I
i l
I l
I I
l l
I 1400 1
~ ~ 1200 1000
~ 800 30 600 20 I
10 8.3 8;0 60 240 52%
70 LOSS OF VOLTAGE OPERATING RANGE 80 320 70~~
90 92 368 80 ~i.
Seconc leve opE'ra tlng region l
(eouipment
)
thermal
~ capability-~
curve)
I 5R J curve' 190 103. 5 110 414 90%
400 I
I
~ 200
~ ~
~
~
tolerance 120 480 104%
SAFEGUARDS ~US VOLTAGE A O ow
-O WQ) fatE 0 4
~Effective 30 days after. completion of necessary modificati ons and no.later than oompletion of the Spring 1982 refueling outage Amendment No.
38 (Correction - Nay 1981)
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NO. of MIN.
MIN.
PERMISSIBLE NO. of CHANNELS OPERABLE DEGREE OF BYPASS CHANNELS TO TRIP CHANNELS REDUNDANCY CONDITIONS
- 17. Circulating Water Flood Protection a.
Screenhouse 2
b.Condenser 6
OPERATOR ACTION, IF CONDITIONS'.OF COLUMN 3 or 5.
CANNOT BE MET,
'ower operation rqpy be continued for a period of up to 7 days with 1 channel inoperable or for a period of 24 ~.
with two channels i~
Power operation may be continued for a period of up to 7 days with 1 channel inoperable or =for a period of.24 hrs.
with two channels inoperable.
O s
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CL B
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Loss of Voltage/
1/
Degraded Voltage 480 Volt Saf'e-.
guards.Bus 4/bus 2/bus 2/bus NOTE 1:
When block condition exists, maintain normal operation.
Maintain hot shut-down or place bus on diesel generator.
F.P.
Full Power Not Applicable If both rod misalignment monitors (a and b) 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 in-creased'urveillance 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.
A channel is considered operable with 1 out of 2 logic or 2 out of 3 logic.
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COO) 0 M MW CD 0 TABLE 4.1-1 (CONTINUED)
Channel Descry nti on Check Calibrate Test 25.
Containment Pressure 26.
Steam Generator Pressure R
20.
Emergency Plan Radiation Instruments 27.
Turbine First Stage Pressure S
Remarks Narrow range containment pressure
(-3.0,
+3 psig excluded) 29.
Environmental Monitors 30.
Los of Voltage/Degraded Voltage 480 Volt Safe-guards Bus N.A.
N.A.
N.A.
0 5
CDOc+0'DB I
CD CO co 00 S
Each Shift D
Daily B/W Biweekly.
Q QuarLerly M
Monthly P
Prior to each startup if not done previous week R
Each Refueling Shutdown N.A. -
Not applicable
r 9 Docket No. 50-244 LS05 Mr, John E. Maier Vice President Electric and Steam Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649
Dear Mr. Maier:
DISTRIBUTION:
Docket NRC PDR LPDR TERA NSIC ORB 85 RF DEisenhut HSmith RPSnaider OELD OI8,E (5)
ACRS (10)
RDiggs JHeltemes Gray File Xtra Cy (6)
By letter dated March 26, 1981, we issued e dment No. 38 to Provisional Operating License No. DPR-18 for the R.
. Ginna Nuclear Power Plant.
Amendment No. 38 approved technical p cifications related to degraded grid voltage protection for the Class power system.,
The amendme t was inadverta y made 'iiffectiv'e upon date of issuance without due considera on for th nstallation of necessary equipment.
In order to necttfy the sttu Ion 1ejheneby modtfy the date of effect1veness oI'hIs amendment (Item 3 o age 2 of Amendment No. 38) to read:
"Thirty (30) days
'fter-.completion~
re ired modifications and no'ater than the completion of the Spring $ 982 Outage.'his/is~the.date which you have stated that such modifications can reaso bly be completed.
A copy of a revised Notice of Is uance is enclosed, Sincerely, Encl osur es)
Revised NoNce. of Issuance, Amendment No. 38 to License No. DPR-18 cc w/enclosure:
See"next page C
Dennis M. Crutchfield, Chief Operating Reactors Branch 85 Division of Licensing OFFICE/
SURNAME/
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..Im'5/j.A HSmith:rj
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RPSnaider
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DCrutchfield OELD PL:AD/$A.
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0 UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-244 ROCHESTER GAS AND ELECTRIC CORPORATION REVISED. NOTICE OF ISSUANCE OF AMENDMENT TO PROVISIONAL OPERATING LICENSE 7590-01 On March 26, 1981,(46 F.R.
212295, April 9, 1981), the U. S. Nuclear Regulatory Commission issued Amendment No. 38 to Provisional Operating License No. DPR-18, to Rochester Gas and Electric Corporation (the licensee),
which revised the technical specifications for operation of the R. E. Ginna Plant (the facility) located in Wayne County, New York.
The amendment was inadvertently made effective upon date of i uance without due consideration for the installation of necessary eq pment.
In order to rectify this situation, by'letter dated 981, the Nuclear Regulatory Commission has modified the date o
effectiveness of Amendment No. 38 to License No.
DPR-18 to be thir
'(30) days after completion of required modifications and.no later than t completion of the Spring 1982 Outage.
The amendment approved requirements regarding deg system.
limitingy nditions for operation and surveillance ded grid voltage protection for the Class IE power The application for the amendment comp with the standards and requirements of the Atomic Energy Act of 1954, as amen edJthe Act), and the Commission s rules and regulations.
The Commission made appropriate findings as required by the Act and the Commission's rules and regulations h
in 10 CFR Chapter I, which are set forth in the license amendment.
Prior public notice of the amendment was not required since the amendment does not involve a significant hazards consideration.
The Commission determined that the issuance of this amendment will not result in any significant environmental impact and that pursuant to 10 CFR 551.5(d)(4) an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with issuance of this amendment.
For further details with respect to this action, see (1) the application for amendment dated September 9,
1980 (transmitted by letter dated September 15, 1980),
as preceded and supported by submittals dated July 21,
- 1977, November 21,
- 1977, December 16, 1977 (transmitted by letter dated December 22, 1977), July 31, 1979 (transmitted August 3, 1979 - two separ ate submittals),
and December 19,
- 1979, (2) Amendment No. 38 to License No. DPR-18, dated March 26,
- 1981, and (3) the Commission's related Safety Evaluation.
All of these items are available for public inspection at the Commission's Public Document
- Room, 1717 H Street, N. W.,
Washington, D. C.
and at the Rochester Public Library, 115 South Avenue, Rochester, New York 14627.
A copy of items (2) and (3) may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D. C.
20555, Attention:
Director, Division of Licensing.
Dated at Bethesda, Maryland, this FOR THE NUCLEAR REGULATORY COMMISSION Dennis M. Crutchfield, Chief Operating Reactors Branch 85 Division of Licensing
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