ML17261A436
| ML17261A436 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/10/1987 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17261A434 | List: |
| References | |
| NUDOCS 8703180216 | |
| Download: ML17261A436 (11) | |
Text
TABLE 3.5-1 INSXEUNENI'PERATION CGNDITICNS Ehge 1 of 3 HNCZIONAL UNIT Manual 4
R)
OF NIN NIN.
PERMISSIBLE R)
OP CtQQIRKS OPERABLE DEGREE OF BYPASS CXiAMELS TO TRIP***
CHANNELS REDUNDANCY CONDITIONS 2
1 1
6 OHRA1QR ACTION IF CONDITIONS OF COLlHN 3 OR 5 CAMVZ BE MET Maintain hot shutdown 2.
Nuclear Flux Power Range Low Setting High Setting 4
4 3.
Nuclear Flux Imtermediate 2
Range 2
2 2 of 4 power range, channels greater than 10% F.P.
(low setting only) 2 of 4 power range channels gr'eater than 10% F.P.
Maintain hot shutdown Maintain= hot shutdown Note 1 Ql I
Cb 4.
Nuclear Flux Source Range
.2 5.
Overtemperature 4 T 6.
Overpower Q T 7.
Low Pressurizer Pressure 8.
Hi Pressurizer Pressure 9.
Pressurizer-Hi Water Level 1 of 2 inter-mediate range channelslareater then 10 'mps Maintain hot shutdown Note 1 Maintain hot shutdown Maintain Maintain hot shutdown hot shutdown Maintain hot shutdown Maintain hot shutdown 10.
0 0
U 11.
Low Flow in One Loop
(> 50% F.P.)
Low Flow Both Loops
"(10-50% F.P.)
Turbine Trip 3/loop 2/loop (any loop) 3/loop 2/loop (any loop) 3
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Maintain hot shutdown Maintain hot shutdown Maintain 50% of Rated Power 870318021b 870310 PDR ADOCK 05000244 p
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TABLE 3.5-1 (Continued)
Page 2 of 3 NO OP NIN NIN.
Pl%MISSIBLE M)
OF CtQHNELS OPERABLE DEGREE OF BYPASS CHAPELS TO TRIP***
CHANNELS REXXM)ANCY 03NDITIONS 6
OPf%MQR ACTIN IF (XNDITIONS OF GXlNN 3'OR 5
~CANK6.'E MET 12; Steam Flow Feedwater Flow Mismatch With Lo Steam Generator Level 2/loop '/loop 1/loop 1/loop
'I Naintain hot shutdown 13.
Lo Lo Steam Generator Water Level 3/loop 2/loop 2/loop 1/loop Maintain hot shutdown 14.
15.
Underyoltage 4KV Bus Underfrequency 4KV Bus 2/bus 1/bus 2/bus 1/bus (both busses) 1/bus 1/bus Naintain hot shutdow Maintain hot shutdown 16.
Quadrant Power Tilt Monitor (Upper 6 Lower Ex-Core Neutron Detectors) 1 or Log individual upper 6 lower ion chamber currents once/hr
& after a load change of 10% or after 48 steps of control rod motion Maintain hot shutdown 3.
17.
Circulating Water Flood Protection
- a. Screenhouse 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;
- b. Condenser 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.
TABLE 3.5-1 (Continued)
Page 3 of 3 2
3 4
5 R). OF NIN NIN PSBNISSIBLE M3 OF CfQNNELS OPl&ABLE DBGRBE OF BYPASS CHANNELS m TRIP***
CHmeELS REDUNDANCY CONDITIONS 6
OPERMQR ACTION IF CON)ITIONS OF CDIIl5N 3 OR 5 CANNOZ BE NET 18.
Loss of Voltage/
Degraded Voltage 480 Volt Safe-guards Bus 4/bus 2/bus 2/bus Naintain hot shutdown or place bus on diesel generator 19.
Automatic Trip Logic
~
. including Reactor Trip Col Breakers Note 2 MEE l:
When block condition exists> maintain normal operation F P Pull Power Not Applicable If a functional unit is operating with the miniraxn 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 oi 2 out of 3 logic 0
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N3TE 2:
Should one reactor trip breaker be inoperable the plant must not be in the operating mode following a six hour tie period. If one of the diverse reactor trip breaker trip features (undervoltage or shunt trip attachment) on one breaker is inoperable>
restore it to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare breaker inoperable.
If at the end of the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period one trip feature is inoperable it must be repaired or the plant must not be in the operating mode following an additional six hour time period.
One reactor trip breaker may be bypassed for surveillance testing provided the other reactor trip breaker is operable.
TABLE 4.1-1 (CONTINUED)
Channel Descri tion Check Calibrate Test 25.
Containment Pressure 26.
Steam Generator Pressure 27.
Turbine First Stage Pressure S
S Narrow range containment pressure
(-3.0I +3 psig) excluded 28.
Emergency Plan Radiation Instruments 29.
Environmental Honitors 30.
Loss of Voltage/Degraded Voltage 480 Volt Safeguards Bus 31.
Trip of Hain Feedwater Pumps 32.
Steam Flow AVG 34.
Chlorine Detectorr Control Room Air Intake NA S
NA 35.
Ammonia Detector r Control Room Air Intake NA 36.
Radiation Detectorsr Control Room Air Intake NA 37a. Trip Breaker Logic Channel Testing NA Note 1 37b. Trip Breaker Logic Channel Testing Note 1
TABLE 4 l-l (CONTINUED)
Dmnnel Descri tion 38 Reactor Trip Breakers Check Calibrate NA NA Test Function test Includes independent testing of both undervoltage and shunt trip attachment of reactor trip breakers.
Each of the two reactor trip breakers will be tested on alternate months.
(Staggered monthly testing) 39.
Manual Reactor Trip NA NA Includes independent testing of both undervoltage and shunt trip circuits.
The test shall also verify the operability of the bypass breaker.
40a. Reactor Trip Bypass Breaker NA NA Using test switches in the reactor protection rack manually trip the reactor trip bypass breaker using the shunt trip coil.
40b. Reactor Trip Bypass Breaker Automatically trip the under-voltage trip attachment.
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'll O-'OTE l: Logic trains will be tested on alternate months corresponding to the reactor trip breaker testing.
Monthly logic testing requires tripping of the reactor trip breaker using one randomly chosen set of actuating contacts.
Refueling shutdown testing of the logic circuitry will verify the operability of all sets of actuating contacts.
In testing< operation of one set of contacts will result in a reactor trip breaker trip; the operation of all other sets of contacts will be verified by the use of indication circuitry.
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ATTACHMENT B This proposed Technical Specification change reflects the request made in the January 9>
1987 NRC letter from Dominic C.
DiIanni to Roger W. Kober concerning the "Review of Design for Automatic Shunt Trip for Reactor Trip Breakers (Generic Letter 83-28 Item 4.3)".
The proposed changes incorporate on-line reactor trip breaker testing into the Technical Specifications and delete a note concerning the date on which a specification was to become effective which has subsequently passed.
A detailed description of all the changes is presented on Table 1.
This change in Technical Specifications clearly is not a request for a change in the authorized power level as it is related only to operational and testing requirements of the reactor trip breakers within the plant.
Further>
the major possible consequence of this change that can be foreseen at this time is that over a period of time additional plant trips may occur through actions taken during monthly testing of the reactor trip breakers.
Howevers occasional trips are considered within the normal operating conditions at a power plant.
A significant hazards analysis has been accomplished against the criteria in 10CFR50.92.
Because the proposed changes constitute additional limitations and control on both operation and testing they do not:
(1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.
Therefore
> Rochester Gas and Electric submits that the issues associated with this amendment request warrant a
no significant hazards finding.
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TABLE 1 Detailed Technical S ecification Chan es Location Description of Change Reason For Change
- p. 3.5-6, Table 3.5-1, Page 1 of 3.
Included item ll of table 3.5-1 on
" Provides consistent typing style page 1 instead of page 2.
for Table 3.5-1 p.
3 '-7, Table 3.5-1, Page 2 of 3.
Delete item ll of table 3.5-1 from Provides consistent typing style this page and add items 17a and 17b for Table 3.5-1.
to the bottom of the page.
- p. 3.5-8, Table 3 '-1, Page 3 of 3.
Delete item 17a and 17b from this page and place on page 2 of 3'.
Add item 19 (Automatic Trip Logic including Reactor Trip Breakers) to this page.
Provides consistent typing style for Table 3.5-1.
This change reflects new operating condition requirements for the reactor trip breakers and reactor trip logic.
Add note 2 to the bottom of this page.
This note is required to explain ful-ly the operator actions required if the requirement of column 3 cannot be met.
Delete 1/ at 'item 18 and related note from the bottom of the page.
Item 18 has been implemented and the effective date for the specification is now moot.
- p. 4.1-7, Table 4.1-1.
Add items 37a and 37b concerning logic testing on a monthly and refueling outage basis.
This addition reflects new testing requirements in response to NRC letter 83-28.
p, 4.1-7a, Table 4.1-1.
Add item 38 concerning the testing of Reactor Trip Breakers.
This addition reflects new testing requirements in response to NRC letter 83-28.
Add -item 39 concerning the testing of the manual tripping of the reactor trip breakers.
This addition reflects new testing requirements in response to NRC letter 83-28.
Add items 40a and 40b concerning the testing of the reactor trip bypass breakers.
Add Note 1
This addition reflects new testing requirements in response to NRC letter 83-28.
This note is required to explain the testing requirements of the logic associated with the reactor trip breakers.
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