ML20151B757

Proposed Tech Specs Re Dcrdr Human Factors Mod

ML20151B757
Person / Time
Site:	Quad Cities
Issue date:	07/07/1988
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20151B748	List: ML20151B745 ML20151B757
References
NUDOCS 8807210090
Download: ML20151B757 (8)

Text

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. *i ATTACIMENT 1 i

PROPOSED CHANGEE_TO APPENDIX _A TECHNICAL SPECIFICATION FOR ,

OUAD CITIES STATION UNIT 2 FACILITY OPERATING LICENSE DPR-30 I

l REVISED PAGES: 3.2/4.2-15 (DPR-30) 3.2/4.2-18 (DPR-30)

! 3.2/4.2-18a (DPR-30) i I

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. DPR-30 TABLE 3.2-4 POSTACCIDENT MONITORING INSTRUMENTATION REQUIRF.MENTSI23 Minimum Instrument Number of Readout Operable Chan- Location Numbe r -

nalg Ill I31 Parameter Unit 2 Provided Ranga 1 Reactor pressure 902-b- 1 0-1500 psig 2 0-1200 psig 1 Reactor water level 902-3 2 -340 inches +60 inches 1 Torus water temperature 902-21 2 0-200*F 1 Torus air temperature 902-21 2 0-600*F Torus water level 902-3 1 -5 inches +5 indicator inches (narrow range) 2(6) Torus water leve'. 902-3 2 0-30 feet indicator (wide range)

Torus water level 1 18 inch range sight glass (narrow range) 1 Torus pressure 902-3 1. -5 inches Hg to 5 psig 2 Drywell pressure 902-3 1 -5 inches Hg to 5 psig

-10 inches Hg to 70 psig 2 -5 to 250 psig 2 Drywell temperature 902-3 6 0-600'F l 2 Neutron monitoring 902-5 4 0.1-108 CPS 2(43 Torus to drywell 2 0-3 psid differential pressure 1(8) Drywell Hydrogen 902-55, 56 2 0-4%

concentration 2(7) Drywell radiation 902-55, 56 2 1 to 108 R/hr monitor Main Steam RV posi- 902-21 1 per NA tion, acoustic monitor valve 2/ valve (5) s  !

Main Steam RV position, 902-21 1 per 0-600'F l temperature monitor valve Main Steam SV posi- 902-21 1 per NA ,

tion, acoustic monitor valve '

2/ valve (5)

Main Steam SV position, 902-21 1 per 0-600'r temperature monitor valve 1285H/ 3.2/4.2-15 Amendment No.

QUAD-CITIES DPR-30 TABLE 4.2-2 POSTACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Minimum Instrument Number of Readout Operable Location Instrument Channels

• Parameter Unit 2 Calibration Chank l 1 Reactor pressure 902-5 Once every 3 months Once per day 1 Reactor water level J02-3 Once every 3 months Once per day 1 Torus water 902-21 _ 1 every 3 months Once per day temperature 1 Torus air 902-21 Once every 3 months Once per day temperature

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Torus water level 902-3 Once every 3 months Once per day (narrow range) 2 - Torus water level 902-3 Once every 18 months Once per 31 Indicator (wide range) days Torus water level N/A None sight glass 1 _ Torus pressure 9U2-3 Once every 3 months Once per day 2 Drywell pressure 902-3 Once every 3 months Once per day 2 Drywell temperature 902-3 Once every 3 months Once per day 2 Neutron monitoring 902-5 Once every 3 months Once per day 2 Torus to drywell Once every 6 months None differential pressure 1 Drywell hydrogen 902-55, 56 Once every 3 months Once per 31 concentration days 2 Drywell radiation 902-55, 56 Once every 18 months Once per 31 monitor *** days Main Steam RV 902-21 ** Once per Position, acoustic 31 days monitor 3/ valve -

Main Steam RV 902-21 Once every 18 months Ouce per Position, 31 days temperature monitor 1285H 3.2/4.2-18 Araendment No. ,

QUAD-CITIES DPR-30 TABLE 4.2-2 (con'd)

Minimum Instrument Numbe r' of Readout Operable Location .

Instrument Channels

• Parameter Unit 2 Calibration Chack Main Cteam SV 902-21 ** Once per l Position, acoustic 31 days monitor 2/ valve .

Main Steam SV 902-21 Once every 18 months Once per l

Position, 31 days

, temperature monitor

• Instrument channels required during power operation to monitor postaccident conditions.

• • Functional tests will be conducted before startup at the end of each refueling outage or af ter maintenance is performed on a particular safety or relief valve.

e** Calibration shall consist of an electronic calibration of the channel, not including the detector, for range decades above 10 R/hr; and a one-point calibration check of the detector below 10 R/hr with an installed or portable gamma source.

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1285H 3.2/4.2-18a Amendment No.

-Q ATTACIBGNT 2

SUMMARY

OF CHANGES Nineteen (19) changes to the Quad Cities Station Unit 2 Technical Specifications have been identified as a result of the proposed license amendment. Two (2) are related to the drywell temperature instrumentation relocation and seventeen (17) correct existing typographical errors. The changes are listed below as follows:

1) Ea.ge 3.2/4.2-15 (DPR-30)

(a) Under column marked "Instrument Readout Location Unit 2", for Parameter titled "Drywell temperature", replace "902-21" with "902-3".

This change reflects the fact'that the drywell temperature indication has been moved from a back panel to a front panel location. Such a change where an instrument location is being revised, is administra-tive in nature.

2) Enge 3.2/4.2-18. Table 4. 2-2. (DPR-30)

(a) Under column marked "Instrument Readout Location Unit 1", replace l "Unit 1" with "Unit 2". -

This change corrects a typographical errcr (Unit 1 when it should be Unit 2 since it pertains to DPR-30). This is an administrative change.

1 (b) Under column marked "Instrument Readout Location Unit 1", (which was l changed to "Instrument Readout Location Unit 2" as described in Item i 2(a)), for all parameters starting with reactor pressure through I Drywell pressure inclusive, change each "901" to "902". There are eight (8) such individual changes whera "901" should be replaced with "902".

Thesa changes are being made to reflect the fact that panels are Unit 2 panels not Unit 1 panels, hence 902 instead of 901. These changes will correct typographical errors that exist in the current Quad Cities Unit 2 Technical Specifications (DPR-30) and is administrative.

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'4 (c) Under column marked "Instrument Readout Location Unit 1", (which was changed to "Instrument Readout Location Unit 2", as described in Item 2(a)), for parameter. titled "Drywell temperature", replace "901-21" with "902-3".

This change reflects the fact that the drywell temperature indication has been moved from a back panel to a front panel location (identical to the change described in 1(a)). Such a change, where.an instrument location is being revised, is administrative in nature.

(d) Under column marked "Instrument Readout Location Unit 1", (which was changed to "Instrument Readout Location Unit 2", as described in Item 2(a)), for all parameters starting with Neutron monitoring through Main Steam RV position, temperature monitor inclusive, change each "901" to "902". There are five (5) such individual changes where "901" should be replaced with "902".

These changes are being made to reflect the fact that panels are Unit 2 panels not Unit 1 panels, hence 902 instead of 901. There changes will correct typographical errors that exist in the current Quad Cities Unit 2 Technical Specifications (DPR-30) and is administrative.

3) EAge 3.2/4.2-13a (DPR-30)

(a) Same change as described in Item 2(a), under column marked "Instrument Readout Location Unit", replace "Unit 1" with "Unit 2".

This change is an administrative change.

ib) Same change as described in Item 2(b). Replace the Instrument Readout Location for the Main Steam SV Position Acoustic Monitor and Main Steam SV Position, Temperature Monitor f rom "901-21" to "902'21.

This change is made in two (2) places on Table 4.2.2. These changes are adminstrative changes.

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. w z ATTACIMENT_.3 EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION AND DESCRIPTION OF PROPOSED AMENDNENT REQUEST There are two types of changes associated with this proposed 11cnese snendment -- both of which are administrative in nature. The first type of chcage results from the completion of a Unit 2 Detailed Control Room Design Review (DCRDR) Human Factors modification which resulted in the relocation of the drywell temperature indicator from the 902-21 (back) panel to the 902-3 (front) panel. Two (2) such changes need to be incorporated into Tables 3.2-4 and 4.2-2 of CPR-30. The remaining seventeen (17) changes correct typogra-phical errors in the existing Technical Specifications.

BASIS FOR NOT SIGNIFICART HAZARDS CW SIDIRATI N Commonwealth Edison has evaluated this proposed amendment and determined that it involves no significant hazards consideration. In accordance with the criteria of 10 CFR 50.92(c), a proposed amendment to an operating license involves no significant hazards consider ations if ope ration of the facility, in accordance with the proposed amendment, would not',

1) Involve a significant increase in the probability or consequences of an accident previously evaluated because:

(a) The location of the drywell temperature indication has been relocated from the back to the front panel in the Control Room which is an enhancement over the past previous location which was approved by the NRC. This is considered to be a change in the conservative direction and therefore, does not result in an increase in the probability or i consequences of previously evaluated accidents.

(b) The other changes merely ce oct typographical errors which have existed in the current Quaa Cities Station Unit 2 Technical Specifications (DPR-30). The correction of typographical errors is considered to be an a&ninistrative change which does not affect the j probability or consequences of previously evaluated accidents. '

2) Create the possibility of a new or different kind of accident from any accident previcusly evaluated because: l (a) There are no hardware changes (addition or deletion of equipment) nor I are there any new modes of operation associated with this amendment.

The changes to Tables 3.2-4 and 4.2-4 reflect changes to equipment (instrumentation) location only. Therefore, the proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.

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(b) The correction of typographical errors does not introduce any new equipment or modes of operation at Quad Cities Station that would create the possibility of a new or different kind of accident than that which was previously evaluated.

3) Involve a significant reduction in the margin of safety because (a) Revising an instrument location readout in the control room does not

-adversely ~ affect the operation of any plant systems. Therefore, the margin of safety has not been unchanged as a result of this change.

(b) The correction of typogr4phical errors is considered to be 4 administrative in nature. There are no changes being made to hardware in the manner that plant system are being operated as a result of this license amendment. -Therefore, the margin of safety is not being compromised as a result of this adminstrative change.

Therefore, since the proposed license amendment satisfies the criteria specified in 10 CFR 50.92, Commonwealth Edison has . determined that a no significant hasards consideration exist for these items. We further request their approval in accordance with the provisions of 10 CFR 50.91(a)(4).

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