ML20059N609
| ML20059N609 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 10/05/1990 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20059N608 | List: |
| References | |
| NUDOCS 9010160372 | |
| Download: ML20059N609 (10) | |
Text
. . . _ .
t ENCLOSURE 1 PLANT HATCH - UNIT 2 NRC DOCKET 50-366 OPERATING LICENSE NPF REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
CHANGES TO ATWS-RPT SPECIFICATION BASIS FOR CHANGE REQUEST PROPOSED CHANGE 1:
Certain proposed changes to Unit 2 Technical Specifications Table 3.3.9.1-1 are necessary.due to the modifications being made to achieve consistency with ATWS Rule 10 CFR 50.62. In Tatle 3.3.9.1-1, the required operable channels per trip system are being changed from "1" to "2" and notes are
-being added or modified to provide for a two-out-of-two logic scheme. In this scheme, either of the two ATWS-RPT trip systems can trip both recirculation _ pumps - Each ATWS-RPT system will trip if two-out-of-two reactor water level 2 signals or two-out-of-two reactor high pressure signals are' received.
In' addition, ' consistent with the two-out-of-twc logic scheme, Technical Specification 3.3.9.1 has been modified to allow unntinued plant operation with an inoperable channel placed in its trip conditicn.
Basis for Proposed Chance 1:
.The current Plant Hatch Unit 2 ATWS-RPT initiation : logic design uses a one-out-of-two logic scheme. .The trip signal is initiated by either c,ne of -
two reactor vessel low water level or one of two reactor vessel high pressure signal s . By letter dated December 14, 1988, the' NRC staff determined a'different logic would be more consistent with the ATWS Rule in
-minimizing inadvertent actuations.- Georgia Power Company selected a
.two-out-of-two logic design.' Accordingly, Table 3.3.9.1-1 of the Unit 2 Technical Specifications is being revised to reflect a two-out-of-two logic scheme.
The . provision to place inoperable channels in their tripped condition and allow continued plant operation is consistent with the current BWR Standard Technical Specifications for a two-out-of-two logic system. Single-failure protection of the plant logic system is maintained while the channel is in the tripped condition.
The pn m .on that allows up to 14 days operation with an inoperable trip system 4 !aing maintained. This LCO time is consistent with the current Plant Haien Unit 2 Technical Specifications and is similar to the BWR Standard Technical Specifications. These changes are also consistent with
-the changes approved by the NRC for Unit 1 in Amendment 169, dated April 27,1990.
9010160372 901005 PDP ADOCK 05000366e r' PNU ~
HL-1296 1101 El-1
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ENCLOSURE:1.(Continued):
REQUEST TO REVISE TECHNICAL SPECIFICATIONS: ;
CHANGES TO ATWS-RPT SPECIFICATION .I BASIS FOR CHANGE RE0 VEST j PROPOSED CHANGE'2:
Certain ' proposed changes-to the Unit 2 Technical Specifications are being l made to provide consistency with the~ current BWR Standard Technical 1 Specifications and the philosophy of Analog Transmitter Trip System (ATTS) design previously approved by the NRC.
In Table 3.3.9.1-2, the allowable values have been changed to be consistent with the calculations performed. for the new equipment. In Table 4'.3.9.1-1, l it is proposed the surveillance frequency for the reactor pressure
' instrument be changed to or.ce per shift (S) for the channel check and the surveillance frequency for the. ATWS-RPT reactor vessel water level and the reactor pressure instrument channel functional tests be changed to once per ~
month (M).
Basis-for Proposed Chanae 2:
~
'The trip' settings for ATWS-RPT currently in the Unit 2 Technical Specifications are based on the setpoint calculation methodology approved by the NRC for ATTS in Amendment 39 to the Unit 2 Technical Specifications,
- i. This methodology calculated allowable values of 1095 psig for the high l
pressure and -47 in. HO 2 for the low water level ATWS-RPT trip settings ,
based on analytical' limits of 1120 psig and -58 in. H2 0, respectively.
This -creates a consistent allowable value and trip setting for 'all the reactor vessel level 2 trip functions. The surveillance frequencies have
= been changed.to be consistent with other equipment installed under the ATTS scope: and are the minimum. assumed in the setpoint calculation.
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HL-1296 1101 El-2 i
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ENCLOSURE 2
-PLANT HATCH - UNIT 2
>< - NRC DOCKET 50-366 ,
OPERATING LICENSE NPF-5 t, *m REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
F CHANGES TO ATWS-RPT SPECIFICATION I l 10 CFR 50.92 EVALUATION C
( PROPOSED CHANGE 1:
As discussed in the Basis for Change Request, certain proposed changes to
. Unit 2 Technical Specifications Table 3.3.9.1-1 are necessary due to-the modifications being made to achieve consistency with ATWS Rule 10 CFR f 50.62. In' Table 3.3.9.1-1, the required operable channels per trip system E 'are being changed from "1" to "2" and notes are being added or modified to provide for a two-out-of-two logic scheme. In this scheme, either of the two ATWS-RPT trip systems can trip both recirculation pumps. Each ATWS-RPT~
l system will trip if_ two-out-of-two reactor water level 2 signals or two-out-of-two reactor high pressure signals are received.
In. addition, consistent with the two-out-of-two logic ' scheme, Technical- i Specification' 3.3.9.1 has been modified to allow continued plant operation- l
-with an inoperable channel placed in its trip condition, l
' Basis for Proposed Chanae 1:
Georgia. Power Company has reviewed the proposed change and determined it does not-involve a safety hazards' consideration based on the- following:
l
- 1. This change does not involve a significant increase in the probability
.or consequences of an accident, because the two-out-of-two logic scheme is designed to reduce inadvertent actuations of the ATWS-RPT trip
, system. .Therefore, overall plant reliability is increased. This design meets the 10 CFR 50.62(c)(5) requirement to automatically trip the. reactor coolant recirculation pumps. The proposed change does not modi fy, degrade, or prevent any actions or assumptions in the current l ATWS analyses. I l
- 2. The possibility of :a different kind of accident from any analyzed previously is not created by this change, since the proposed change is consistent with the ATWS Rule. The ATWS-liPT logic would be changed to
--two-out-of-two to minimize inadvertent actuations and allow maintenance testing or calibration during power operation.
- 3. Margins of safety are not significantly reduced by this change, since the provision to place an inoperable channel in the tripped condition and allow continued plant operation is consistent with the current BWR Standard Technical Specifications for a two-out-of-two logic system.
I HL-1296 1101 E2-1
.1 4
ENCLOSURE 2.(Continued)
REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
CHANGES TO ATWS-RPT SPECIFICATION
- 10 CFR 50.92 EVALUATION l
- l While in this LC0 condition, single-failure capability of the plant j logic; system is maintained while the channel is in the tripped 1 J condition. If a complete trip system is inoperable, the 14-day LCO for i continued plant operation will be maintained. l 1: l PROPOSED CHANGE 2:
As discussed in the Basis for Change Request, certain proposed changes to the Unit 2 Technical Specifications are being made to be consistent with the current BWR Standard Technical Specifications and the philosophy'of Analog Transmitter Trip. System (ATTS) design previously approved by the NRC. l l
- In Table 3.3.9.1-2, the allowable values have been changed to be consistent with the calculations performed for the new design. The calculations are ,i based on a rigorous setpoint calculation methodology meeting the L requirements of Regulatory Guide 1.105 and approved by the NRC-in previous ,
In Table 4.3.9.1-1, it is proposed the Plant Hatch amendments. !
surveillance frequency for the reactor pressure instrument be changed to once per shift (S) for the channel check and the surveillance frequency for the ATWS-RPT reactor vessel water level and the reactor pressure instrument
' channel functional test be changed to once per month (M).
Basis for Proposed Chanae 2:
l
!, Georgia Power Company has reviewed the proposed change and determined it does not involve a safety hazards consideration based on-the following:
- l. This change does not involve a significant increase in the probability or consequences of an accident, since the plant analytical limits will remain unchanged. The proposed changes to Table 4.3.9.1-1 require more frequent instrumentation checks and functional testing than are presently specified. The changes are consistent with the NRC-approved surveillances for the ATTS design in Unit 2 Technical Specifications !
Amendment 39, thereby providing equal or better assurance of system availability.
- 2. The possibility of a different kind of accident from any analyzed previously is not created by this change, since the proposed change of using allowable values for the ATWS-RPT reactor vessel water level trip function-does not change any plant failure modes.
HL-1296 L 1101 f2-2
ENCLOSURE 2 (Continued).
REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
CHANGES TO ATWS-RPT SPECIFICATION 10 CFR 50.92 EVALUATION p
' 3. Margins of safety are not significantly reduced by this change, since the ATWERPT reactor vessel low water level and reactor high pressure trip settings are calculated using the setpoint calculation methodology approved by the NRC for ATTS in Amendment 39 to the Unit 2 Technical Specifications. This methodology caiculated allowable values of'1095 l;-
l~ psig for the high pressure and -47 in. H20 for the level 2 reactor vessel- water level- ATWS-RPT trip settings._ The new surveillance frequencies are also based on the methodology and the overall design aspects of ATTS.
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- HL-1296 1101 E2-3
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ENCLOSVRE 3 PLANT HATCH - UNIT 2 NRC DOCKET 50-366 l OPERATING LICENSE.NPF-5 REQUEST TO REVISE. TECHNICAL SPECIFICATIONS:'
CHANGES TO ATWS-RPT SPECIFICATION PAGE CHANGE INSTRUCTIONS The proposed changes to the Plant ' Hatch Unit 2 Technical Specifications (Appendix A to Operating License NPF-5) will be incorporated.as follows: ,
Remove Paae Insert Paae I 3/4 3-66 3/4 3-66 1
3/4 3-67 3/4 3-67 ,
l 3/4 3-68 3/4 3-68 j i 3/4 3-69 3/4 3-69 l
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HL-1296 1101 E3-1
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> . INSTRUMENTATION 3/4.3.9 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATHS RECIRCULATION =ruMF TRIF sisiEh INSTRUMENTATION LIMITING CONDITION FOR OPERATION ,
3.3.9.1 The anticipated transient without scram recirculation pump-trip (ATHS-8P,T) system instrumentation channels shown in Table 3.3.9.1-1 shall be OPERABLE with their trip setpoints set consistent with values shown in the Trip Setpoint column of Table 3.3.9.1-2.
~
APPLICABILITY: OPERATIONAL CONDITION 1.
ACTION:
- a. With an ATHS recirculation pump trip system instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.9.1-2, declare the channel inoperable until the channel is restored to OPERABLE status with the channel trip setpoint adjusted consistent with the Trip Setpoint value,
- b. With-the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels per Trip System requirement for one.or both trip systems, place the inoperable channel in the tripped condition l' within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- c. With the number of OPERABLE channels two less than required by the l~
Minimum OPERABLE Channels per Trip System requirement for one trip system and, i 1. If the inoperable channels consist of one reactor vessel water L
level channel and one reactor vessel pressure channel, place both inoperable channels in the tripped condition within I hour. ,
- 2. If the inoperable channels -include two reactor vessel water level channels or two reactor vessel pressure channels, declare the trip = system inoperable. ,
-d. With one trip system inoperable, restore the inoperable tr'o. system to OPERABLE status within 14 days or be in at least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- e. Hith both trip systems inoperable, restore at least one trip system '
to OPERABLE status within l' hour or be in at least STARTUP within the-next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS
- 4. 3. 9.1.1 - Each ATHS recirculation pump trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.9.1-1.
4.3.9.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be perforned at least once per 18 months.
' HATCH - UNIT 2 3/4 3-66 Proposed TS/0393q/254-69
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