Proposed Tech Specs Adding Two Smoke Detectors & Room Numbers to Table 3.3.7.9-1 as Well as Renaming Room Described in Table 3.3.7.9-1 as Result of Design ChangesML20006E156 |
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Site: |
Grand Gulf |
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Issue date: |
02/09/1990 |
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From: |
SYSTEM ENERGY RESOURCES, INC. |
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To: |
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Shared Package |
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ML20006E155 |
List: |
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References |
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NUDOCS 9002220198 |
Download: ML20006E156 (6) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211E7151999-08-20020 August 1999 Proposed Tech Specs,Incorporating Many Generic Improvements Agreed Upon Between Industry & NRC Since GGNS Conversion to ITS ML20196K0831999-06-29029 June 1999 Proposed Tech Specs Page 3.4-3,reflecting Implementation of BWROG Enhanced Option I-A,reactor Stability long-term Solution ML20196G7131999-06-23023 June 1999 Proposed Tech Specs Revising TS Associated with Various Esfss Which Need No Longer Be Credited Following Design Basis Fuel Handling Accident ML20206K5361999-05-0606 May 1999 Proposed Tech Specs Pages,Changing SLMCPR ML20206R9351999-01-12012 January 1999 Proposed Tech Specs Re Refueling Equipment Interlocks Required Actions ML20154Q4511998-10-16016 October 1998 TS Bases Update for Period of 970410 Through 981015 ML20236T1661998-07-20020 July 1998 Proposed Tech Specs 3.2.4,3.3.1.1,3.3.1.3,3.4.1,5.6.5, B 3.2.4,B 3.3.1.1,B 3.3.1.3 & B 3.4.1,enabling Full Implementation of Enhanced Option I-A Long Term Solution to Address Neutronic/Thermal Hydraulic Instability Issue ML20198J3581998-01-0909 January 1998 Proposed Tech Specs,Providing Certain Clarifications to Amend & Adding Restriction to Allowed Interval Extensoions ML20198N3941997-10-28028 October 1997 Proposed Tech Specs Implementing Option B & Ref SE Issued by NRR for Ggns'S App J Exemption as Implementing Document for performance-based Leakage Testing Program ML20211M8481997-10-0606 October 1997 Proposed Tech Specs Replacement Bases Pages Associated W/Proposed Amend to License Re Response Time Testing ML20210V5581997-09-18018 September 1997 Proposed Tech Specs Reflecting Decrease of Two Recirculation Loop SLMCPR Limit to 1.11 & Single Recirculation Loop SLMCPR Limit to 1.12 ML20210H0871997-08-0606 August 1997 Proposed Tech Specs Changing TS 3.8.1, AC Sources Operating. Removal of Accelerated Testing Requirements for Standby DGs as Advised by GL 94-01 ML20141A1681997-05-0707 May 1997 Proposed Tech Specs Re Eliminating Selected Response Time Testing Requirements ML20140E3211997-04-18018 April 1997 Proposed Tech Specs,Revising TS Bases to Include Changes Made Since Rev 1 Was Sent to NRC 960201 ML20134N7841996-11-21021 November 1996 Proposed Tech Specs Pp 5.0-20 & 5.0-21,revised by Adding Footnote Indicating Proposed Change Applicable Only for Cycle 9 ML20134N7611996-11-20020 November 1996 Proposed Tech Specs Re MCPR Limits for Two Recirculation Loop Operation ML20134E1261996-10-22022 October 1996 Proposed Tech Specs Revising TS Figure 3.4.11-1, Minimum Reactor Vessel Metal Temperature Vs Reactor Vessel Procedure, Curves Using Methodology of NRC Reg Guide 1.99, Rev 2, Radiation Embrittlement of Reactor Vessel Matls ML20128M5681996-10-0909 October 1996 Proposed Tech Specs 3.8.1.14 Re Surveillance Requirements ML20117P4461996-09-19019 September 1996 Proposed Tech Specs Re Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency ML20117M7021996-09-0505 September 1996 Proposed Tech Specs Re Min Critical Power Safety Limit ML20117G6781996-08-27027 August 1996 Proposed Tech Specs Re Surveillance Requirements for Safety/Relief Valves ML20116F0211996-07-31031 July 1996 Proposed Tech Specs Required to Support Cycle 9,reload 8 ML20113B7381996-06-20020 June 1996 Proposed Tech Specs,Redefining Secondary Containment Boundary to Allow Encl Bldg to Be Inoperable During Upcoming Refueling Outage ML20117L2581996-06-0404 June 1996 Proposed Tech Specs Re Replacement Page for Ltr RBG-42764, Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks1996-05-31031 May 1996 Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks ML20117F4661996-05-0909 May 1996 Proposed Tech Specs,Modifying SRV Surveillance Test for Relief Mode of Operation ML20117D6941996-05-0909 May 1996 Proposed Tech Specs Required to Support Unit 1 Cycle 9, Including Changes to SLMCPR & Ref for Analytical Methods Used to Determine Core Operating Limits.Addl Methodology Ref in Various TS Bases Revised to Reflect GE Methodologies ML20111B2701996-05-0808 May 1996 Proposed Tech Specs,Placing Containment Purge Valves W/ Resilient Seals on Performance Based Leakage Testing Frequency ML20108E3591996-05-0606 May 1996 Proposed Tech Specs Re Change in Co Name from Mississipi Power & Light to Entergy Mississippi,Inc ML20107E4681996-04-18018 April 1996 Proposed Tech Specs Re Fuel Loading W/Control Rods Withdrawn or Removed from Defueled Core Cells ML20100J8391996-02-22022 February 1996 Proposed Tech Specs Re Safety Setpoint Tolerance Requirements for Safety/Relief Valves ML20097C3541996-02-0101 February 1996 Proposed Tech Specs,Revising TS Bases to Include Changes Since 950221 Approval of TS Bases ML20094M8001995-11-20020 November 1995 Proposed Tech Specs Re Drywell Leak Rate Testing Requirements ML20087B5061995-08-0404 August 1995 Proposed Tech Specs Assoc W/Various ESF Sys Following Design Basis Fuel Handling Accident ML20082K3451995-04-13013 April 1995 Proposed Tech Specs Re Change to Be Reduced to Leave in TS Requirement to Test Outboard MSIV LCS Blowers ML20078S5141995-02-14014 February 1995 Proposed TS Consisting of Changes to SR 4.4.1.4.a.1 & 4.6.1.4.a.2 ML20078N6611995-02-10010 February 1995 Proposed Tech Specs Supporting Performance of Drywell Bypass Leakage Rate Surveillance on Performance Based Interval ML20079B4501994-11-0909 November 1994 Proposed Tech Specs Associated W/Various ESF Systems Following Design Basis Fuel Handling Accident ML20070C9751994-06-24024 June 1994 Proposed TS Pages 3/4 6-4 & 3/4 6-6 Associated W/Proposed Exemption to 10CFR50,App J ML20065L4971994-04-15015 April 1994 Proposed Tech Specs Re Administrative Controls ML20059H6061994-01-13013 January 1994 Proposed Tech Specs,Removing 2,324 Spent Fuel Pool Storage Limit ML20058D3911993-11-23023 November 1993 Proposed Tech Specs Bases Pages Re Cycle 7 Reload ML20059A4871993-10-22022 October 1993 Proposed Tech Specs Modifying Testing Frequencies for Drywell Test & Airlock Tests ML20059B0351993-10-15015 October 1993 Proposed Tech Specs Converting Current GGNS TS to TS Based Largely on NUREG-1434,Rev 0 ML20057C7281993-09-23023 September 1993 Proposed Tech Specs Removing Surveillance Requirement 4.4.1.2.2 Due to Problems Encountered W/Jet Pump Differential Pressure Instrumentation Measurements ML20056E4511993-08-12012 August 1993 Proposed Tech Specs 3/4 6-3,6-4,6-4a,6-6,6-12 Re Exemption to 10CFR50,App J, Primary Reactor Containment..., for Local Leak Rate ML20056D5621993-08-11011 August 1993 Proposed Tech Specs Section 3/4.3.7.5 Reflecting Relocation of Certain Accident Monitoring Instrumentation to Administrative Control ML20046D2081993-08-11011 August 1993 Proposed Tech Specs Section 3/4.3.7.10, Loose Part Detection Sys, Relocating Loose Part Detection Instrumentation from TS to Administrative Control ML20046D1961993-08-11011 August 1993 Proposed Tech Specs Supporting Compliance W/New Requirements of 10CFR20 & 10CFR50.36a ML20056C7141993-07-15015 July 1993 Proposed Tech Specs Removing Operability Requirements for auto-test Feature of Load Shedding & Sequencing Sys & Increase AOT for Inoperable Load Shedding & Sequencing Sys from Eight to Twelve 1999-08-20
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211E7151999-08-20020 August 1999 Proposed Tech Specs,Incorporating Many Generic Improvements Agreed Upon Between Industry & NRC Since GGNS Conversion to ITS ML20196K0831999-06-29029 June 1999 Proposed Tech Specs Page 3.4-3,reflecting Implementation of BWROG Enhanced Option I-A,reactor Stability long-term Solution ML20196G7131999-06-23023 June 1999 Proposed Tech Specs Revising TS Associated with Various Esfss Which Need No Longer Be Credited Following Design Basis Fuel Handling Accident ML20206K5361999-05-0606 May 1999 Proposed Tech Specs Pages,Changing SLMCPR ML20206R9351999-01-12012 January 1999 Proposed Tech Specs Re Refueling Equipment Interlocks Required Actions ML20154Q4511998-10-16016 October 1998 TS Bases Update for Period of 970410 Through 981015 ML20236T1661998-07-20020 July 1998 Proposed Tech Specs 3.2.4,3.3.1.1,3.3.1.3,3.4.1,5.6.5, B 3.2.4,B 3.3.1.1,B 3.3.1.3 & B 3.4.1,enabling Full Implementation of Enhanced Option I-A Long Term Solution to Address Neutronic/Thermal Hydraulic Instability Issue ML20198J3581998-01-0909 January 1998 Proposed Tech Specs,Providing Certain Clarifications to Amend & Adding Restriction to Allowed Interval Extensoions ML20210F6651997-12-22022 December 1997 Redeacted Version of Test Rept M-J5.08-Q1-45161-0-8.0-1-0, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators for Entergy Operations ML20217H6211997-12-15015 December 1997 Rev 21 to Odcm ML20199L5711997-11-26026 November 1997 Rev 8 to Program Plan GGNS-M-189.1, Grand Gulf Nuclear Station Pump & Valve IST Program - Safety Related ML20198N3231997-11-0606 November 1997 Rev 11 to GGNS-M-489.1, Program Plan for ASME Section XI ISI Plan ML20198N3941997-10-28028 October 1997 Proposed Tech Specs Implementing Option B & Ref SE Issued by NRR for Ggns'S App J Exemption as Implementing Document for performance-based Leakage Testing Program ML20211M8481997-10-0606 October 1997 Proposed Tech Specs Replacement Bases Pages Associated W/Proposed Amend to License Re Response Time Testing ML20210V5581997-09-18018 September 1997 Proposed Tech Specs Reflecting Decrease of Two Recirculation Loop SLMCPR Limit to 1.11 & Single Recirculation Loop SLMCPR Limit to 1.12 ML20210H0871997-08-0606 August 1997 Proposed Tech Specs Changing TS 3.8.1, AC Sources Operating. Removal of Accelerated Testing Requirements for Standby DGs as Advised by GL 94-01 ML20141A1681997-05-0707 May 1997 Proposed Tech Specs Re Eliminating Selected Response Time Testing Requirements ML20140E3211997-04-18018 April 1997 Proposed Tech Specs,Revising TS Bases to Include Changes Made Since Rev 1 Was Sent to NRC 960201 ML20134N7841996-11-21021 November 1996 Proposed Tech Specs Pp 5.0-20 & 5.0-21,revised by Adding Footnote Indicating Proposed Change Applicable Only for Cycle 9 ML20134N7611996-11-20020 November 1996 Proposed Tech Specs Re MCPR Limits for Two Recirculation Loop Operation ML20134E1261996-10-22022 October 1996 Proposed Tech Specs Revising TS Figure 3.4.11-1, Minimum Reactor Vessel Metal Temperature Vs Reactor Vessel Procedure, Curves Using Methodology of NRC Reg Guide 1.99, Rev 2, Radiation Embrittlement of Reactor Vessel Matls ML20128M5681996-10-0909 October 1996 Proposed Tech Specs 3.8.1.14 Re Surveillance Requirements ML20117P4461996-09-19019 September 1996 Proposed Tech Specs Re Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency ML20117M7021996-09-0505 September 1996 Proposed Tech Specs Re Min Critical Power Safety Limit ML20117G6781996-08-27027 August 1996 Proposed Tech Specs Re Surveillance Requirements for Safety/Relief Valves ML20116F0211996-07-31031 July 1996 Proposed Tech Specs Required to Support Cycle 9,reload 8 ML20113B7381996-06-20020 June 1996 Proposed Tech Specs,Redefining Secondary Containment Boundary to Allow Encl Bldg to Be Inoperable During Upcoming Refueling Outage ML20117L2581996-06-0404 June 1996 Proposed Tech Specs Re Replacement Page for Ltr RBG-42764, Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks1996-05-31031 May 1996 Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks ML20117D6941996-05-0909 May 1996 Proposed Tech Specs Required to Support Unit 1 Cycle 9, Including Changes to SLMCPR & Ref for Analytical Methods Used to Determine Core Operating Limits.Addl Methodology Ref in Various TS Bases Revised to Reflect GE Methodologies ML20117F4661996-05-0909 May 1996 Proposed Tech Specs,Modifying SRV Surveillance Test for Relief Mode of Operation ML20111B2701996-05-0808 May 1996 Proposed Tech Specs,Placing Containment Purge Valves W/ Resilient Seals on Performance Based Leakage Testing Frequency ML20108E3591996-05-0606 May 1996 Proposed Tech Specs Re Change in Co Name from Mississipi Power & Light to Entergy Mississippi,Inc ML20107E4681996-04-18018 April 1996 Proposed Tech Specs Re Fuel Loading W/Control Rods Withdrawn or Removed from Defueled Core Cells ML20100J8391996-02-22022 February 1996 Proposed Tech Specs Re Safety Setpoint Tolerance Requirements for Safety/Relief Valves ML20097C3541996-02-0101 February 1996 Proposed Tech Specs,Revising TS Bases to Include Changes Since 950221 Approval of TS Bases ML20094M8001995-11-20020 November 1995 Proposed Tech Specs Re Drywell Leak Rate Testing Requirements ML20087B5061995-08-0404 August 1995 Proposed Tech Specs Assoc W/Various ESF Sys Following Design Basis Fuel Handling Accident ML20082K3451995-04-13013 April 1995 Proposed Tech Specs Re Change to Be Reduced to Leave in TS Requirement to Test Outboard MSIV LCS Blowers ML20108A2691995-03-10010 March 1995 Rev 17 to ODCM ML20078S5141995-02-14014 February 1995 Proposed TS Consisting of Changes to SR 4.4.1.4.a.1 & 4.6.1.4.a.2 ML20078N6611995-02-10010 February 1995 Proposed Tech Specs Supporting Performance of Drywell Bypass Leakage Rate Surveillance on Performance Based Interval ML20079B4501994-11-0909 November 1994 Proposed Tech Specs Associated W/Various ESF Systems Following Design Basis Fuel Handling Accident ML20070C9751994-06-24024 June 1994 Proposed TS Pages 3/4 6-4 & 3/4 6-6 Associated W/Proposed Exemption to 10CFR50,App J ML20065L4971994-04-15015 April 1994 Proposed Tech Specs Re Administrative Controls ML20059H6101994-01-14014 January 1994 Cycle 7 Startup Physics Test Summary Rept for Physics Testing Completed on 931220 ML20059H6061994-01-13013 January 1994 Proposed Tech Specs,Removing 2,324 Spent Fuel Pool Storage Limit ML20029D6451993-11-30030 November 1993 Reactor Containment Bldg 1993 Integrated Leakage Rate Test. ML20058D3911993-11-23023 November 1993 Proposed Tech Specs Bases Pages Re Cycle 7 Reload ML20059A4871993-10-22022 October 1993 Proposed Tech Specs Modifying Testing Frequencies for Drywell Test & Airlock Tests 1999-08-20
[Table view] |
Text
A in .. - Attachment 2 to AECM-90/0011 Page 1 of 3 l
A. SUBJECT
- 1. NPE 89/01 Addition of two smoke detectors to Table 3.3.7.9-1 2.- NPE 89/02 Rename room in Table 3.3.7.9-1
- 3. Revised Technical Specification:
- a. Fire Detection Instrumentation, Table 3.3.7.9-1, Pages 3/4 3-81 and 3/4 3-86 B. DISCUSSION
- 1. Table 3.3.7.9-1 is being revised to reflect a design change to construct a non-safety related, permanent facility to house snubber test equipment and personnel necessary to test snubbers in accordance with Technical Specification 3/4.7.4. This new, totally enclosed facility will be located in Fire Zone 1A519 of the Auxiliary Building at elevation 185'-0" and will be partitioned into a " Snubber Test Room" and a " Snubber Test Control Room." Attachment 3 provides a general layout of the facility. The Snubber Test Facility will not house any safety-related equipment; however, it will be located within Fire Area 19 which contains some safety-related equipment. Since this enclosure could effectively isolate a fire occurring inside the Snubber Test Facility from fire detectors which are exterior to the facility for an indeterminate period of time, this design change includes the addition of a detector in both the " Snubber Test Control Room" and the " Snubber Test Room." Therefore, Table 3.3.7.9-1 is being revised to reflect the additional instruments in Detection Zone 2-9.
2.- Table 3.3.7.9-1 is also being revised to reflect renovation of the 93'-0" elevation of the Control Building, north of central corridor 0C115. The renovation will provide better space utilization and facility upgrade to accommodate the personnel needs of the GGNS Health Physics organization. As a result of this renovation, the room name for Room Number 0C103 will be changed from " Emergency Laundry Room" to "HP Checkout."
l C. JUSTIFICATION l
- 1. The new, permanent Snubber Test Facility will be nonsafety-related and will not house any safety-related equipment. To minimize impact on fire protection, all construction and finishing materials will be ;
non-combustible as defined in the Fire Hazards Analysis. The ;
facility will also be provided with a smoke detector in each of the two rooms to provide early warning and thus reduce the potential for fire damage to safety-related equipment adjacent to the Snubber Test !
Facility.
- 2. The addition of two smoke detectors, along with accessibility to .
existing manual hose streams and portable fire extinguishers, will !
provide adequate fire protection capability for this facility.
^
A9100502/SNLICFLR - 5 9002220198 900209 PDR ADOCK 05000416 P PDC
, . Attachment 2 to AECM-90/0011 Page 2 of 3
- 3. The renovation of the 93'-0" Elevation of the Control Building will not result in the removal of any fire detection instrumentation.
The level of smoke detection capability will not be reduced by the renovation. The renovation will not affect any fire area boundaries as described in Revision 3 of the Fire Hazards Analysis. Therefore, the current level of fire protection will not be reduced.
D. NO SIGNIFICANT HAZARDS CONSIDERATIONS SERI is proposing with this amendment request a revision to TS Table 3.3.7.9-1 which would:
- 1. Add two smoke detectors and rooms to reflect the construction of a new Snubber Test Facility.
- 2. Revise the room name for Room Number 0C103 from " Emergency Laundry Room" to "HP Checkout" due to renovation of the Control Building.
The Commission has provided standards for determining whether a no significant hazards consideration exists as stated in 10CFRSO.92(c). A proposed amendment to an operating license involves no significant hazards consideration if operation 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; 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.
SERI has evaluated the no significant hazards considerations in its request for a license amendment. In accordance with 10CFR50.91(a), SERI is providing the analysis of the proposed amendment against the three standards in 10CFR50.92:
- 1. No significant increase in the probability or consequences of an accident previously evaluated results from this change.
- a. The proposed change expands an existing smoke detection zone to monitor two new rooms and their respective fire hazards.
Consequently, the level of smoke detection capability will not be reduced. The analysis of safe shutdown in the event of a fire (UFSAR Appendix 9C) is not adversely affected by this change,
- b. The renovation of the 93'-0" Elevation of the Control Building will not add, remove, or relocate any fire detection instrumentation identified in Technical Specification Table 3.3.7.9-1. The proposed change renames an existing room and does not reduce the level of smoke detection capability. The analysis of safe shutdown in the event of a fire (UFSAR Appendix
- 90) is not adversely affected by this change.
i
- c. Therefore, there is no increase in the probability or consequences of a previously analyzed accident due to this change.
A9100502/SNLICFLR - 6 e J
9 s.
Attachment 2 to AECM-90/0011
(
Page 3 of 3 >
1
- 2. This change would not create the possibi'lity of a new or different kind of accident from any previously evaluated, t :
The proposed changes do not postulate fires in areas of the
- a. '
plant in which fires were not previously postulated and no new f_ or different failure modes are created. The first change will !
expand an existing smoke detection zone to monitor two new rooms .
t and their respective fire hazards. The second change does not add, remove or relocate any fire detection instrumentation ,
identified in Technical Specification Table 3.3.7.9-1 but renames a room identified in the Table, ,
e
- b. Therefore, the possibility of a new or different kind of I accident from any previously evaluated is not created.
- 3. This change would not involve a significant reduction in the margin .
of safety.
I a. The bases for Technical Specification 3.3.7.9, as it relates to the proposed changes, is to ensure availability of adequate warning capability for prompt detection of fires. Consequently, prompt detection of fires will reduce the potential for damage ;
to safety-related equipment,
- b. Expanding Detection Zone 2-9 to monitor two newly created rooms and their respective fire hazards will maintain the existing
identified in Technical Specification Table 3.3.7.9-1 will not !
reduce the present level of fire detection and does not compromise the bases for this Technical Specification. .
- c. Therefore, this proposed change will not involve a significant !
reduction in the margin of safety. '
Therefore, based on the above evaluation, operation in accordance with the proposed amendment involves no significant hazards considerations, t
r A9100502/SNLICFLR - 7 L
.- N P r. s s / oi so f*fa $W h l k M8bieM'm 48f.m l
. TABLE 3.3.7.9-1 (Continued) 87/>6 %,dahd MayM,ltlT l FIRE DETECTION INSTRUMENTATION
)
MINIMUM INSTRUMENTS OPERABLE
ROOM ELEV ROOM NAME F E SM0 Kell}
} M
- 7. Zone 2-8 27/0 1A401 166' Northeast Corridor 1A402 166' Steam Tunnel Roof i L 1A403 166'- Southeast Corridor i 1A404 166' Unassigned Area 1A405 166' Containment Vent.
Equip. Room 1A406 166' Containment Exhaust Filter Rm.
1A407 166' MCC Area 0/2(C03 )
1A410 166' MCC Area 0/2(C0a) 1A417 166' NorthCorridor(Partial) l 1A420 166' SouthCorridor(Partial) 1A424 166' Set _Doyn Area (Parti _al)__ _
l l- 8. Zone 2-9 liA 145 tAsl96 138,'Ewbber-Te&+
symbbsr TsaiAcom Contnl Room
! ,1A519 185' Storage Area l 1A524 195' Platform '
1A527 185' Load Center Area 1A529 185' FPC & CU Rm.
1A538 185' Platform
- 9. Zone 2-13 31/0' 1A602 -208' Storage Area 1A603 208' Passage 1A604 208' Fuel Handling Area IA606 245' HVAC Equip. Area
- 10. Zone 2-14 17/0 1A114 93' Fan Coil Area (Partial) 1A115 93' Piping Penetration Rm.
1A116 93' Piping Penetration Rm. ,
1A117 93' Misc. Equip. Area !
(Partial) 1A118 93' RHR "C" Pump Room 1A119 93' LPCS Pump Room 1A120 93' CCW Pump & Heat Ex. Rm.
1A122 103' SouthCorridor(Partial) 1A123 103' North Corridor (Partial)
- 11. Zone 2-15 1/0 1A539 185' Cable Chase GRAND GULF-UNIT 1 3/4 3*S6 Amendment No. 42 3 t
. NPE $9/0,t. .
i
' Poe. c.wo+.d +m be dele.tedin AEcm !
87/oo%/ded NYM,1987 TABLE 3.3.7.9-1 .
FIRE DET N NTATION !
MINIMUM INSTRUMENTS OPERABLE" f ll} !
. INSTRUMENT LOCATION HEAT FgE SM0 Kell)
- a. CONTAINMENT SUILDING #
@) D/TJ M !
- 1. Return Duct Mounted Detectors 3/0
_ ROOM ELEV ROOM NAME !
- b. CONTROL BUILDING
- 1. Zone 1-3 -- - -
12/0
. Gue2 ' is7 H.P. chukoht) ,
== r : , ;. r.;, 1. .. .; , L . :
0C109 93' Decontamination Area i 0C115 93' Corridor !
l 0C116 93' Hot Machine Shep 0C117 93' Corridor 0C128 93' Hot Water Heater Rm.
- j. 2. Zone 1-4 12/0 l
OC201 111' Stairvell 0C202 111' Div. I Swgr. Rs. 0/13(C0e) p I OC207 111' Div. I Battery Rm.
p i i
(X/Y): X - is number of Function A (early warning fire detection and notification only) instruments. .
Y - is number of Function B (actuation of fire suppression systems i and early warning and notification) instruments. !
- The fire detection instruments located within the primary containment are not required to be OPERABLE during the performance of Type A Containment ,
Leakage Rate Tests.
l~ (1) Smoke and flame detectors provide only early warning capability with the '
exception of:
(a) Zone 1-27 detectors trip closed the door between the OC208/0C208A ,
Remote Shutdown panel rooms.
(b) Containment building return duct mounted detectors trip the '
containment cooler fans.
(c) Zone 1-11 and 1-13 detectors initiate the control building purge fan system. .
! (d) Control Room HVAC Intake Plenum Detectors trip the control room A/C units unless a control room emergency filtration system isolation mode automatic actuation signal is present.
GRAND GULF-UNIT 1 3/4 3-81 Amendment No. 42;-
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