Proposed Tech Spec Changes as Result of Recent Design Change to Allow Addition of Sprinklers to Area IA424 to Add More Accessible Containment Isolation Valve E12-F394. W/Significant Hazards ConsiderationML20154A195 |
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Grand Gulf |
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Issue date: |
02/28/1986 |
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From: |
MISSISSIPPI POWER & LIGHT CO. |
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To: |
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Shared Package |
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ML20154A172 |
List: |
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References |
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TAC-60863, TAC-60864, NUDOCS 8603030332 |
Download: ML20154A195 (5) |
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Category:TECHNICAL SPECIFICATIONS
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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] |
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TA8LE 3.6.4-1 CONTAINMENT AND ORYWELL I5OLATION VALVES '
MAXImm SYSTEM AND PENETRATION ISOLATION TIME VALVE NUMBER NUMBER VALVE GROUP I ") (Seconds)
- 1. Automatic Isolation Valves #
- a. Containment i Main Steam Lines B21-F028A 5(0)* 1 . 5 i Main Steam Lines 821-F022A 5(I)* 1 5
- Main Steam Lines 821-F067A-A 5(0)* 1 9
) Main Steam Lines 321-F0288 6(0)* 1 5
) Main Steam Lines 521-F0228 6(I)* 1 5 j Main Steam Lines 521-F0678-A 6(0)* 1 9
! Main Steam Lines . 821-F028C 7(0)* 1 5
- Main Steam Lines 821-F022C 7(I)* 1 5
, Main Steam Lines 321-F067C-A 7(0)* 1 9 l'
Main Steam Lines 821-F0280 8(0)* 1 5 Main Steam Lines 821-F022D 8(I)* 1 5
- Main Steam Lines 821-F067D-A 8(0)* 1 9
! RHR Reactor E12-F008-A 14(0) 3 40 Shutdown Cooling i
Suction i RHR Reactor E12-F009-B 14(I) 3 40 l Shutdown Cooling Suction Steam Supply to E51-F063-B 17(I) , 4 - 20
, RHR and RCIC Turbine i
Steam Supply to E51-F064-A 17(0) 4 20 RHR and RCIC Turbine ..
I Steam Supply to E51-F076-8 17(I) 4 20
! RHR and RCIC Turbine RHR to Head Spray E12-F023-A 18(0) 3 O 94 RHR to Head Spray E12-F394-8 18(I) 3 l+- 8 l (a) See Specification 3.3.2, Table 3.3.2-1, for isolation signal (s) that
- operates each valve group.
(b) Deleted
} (c) Hydrostatically tested with water to 1.10 P 4
(d) HydrostaticallytestedbypressurizingsystIm,12.65psig. to 1.10 P (e) Hydrostatically tested during system functional tests. ,, 12.65 psig.
(f) Deleted
! (g) Normally closed or locked closed manual valves may be opened on an ,
! intermittent basis under administrative control. !
- *The provisions of Specification 4.0.4 are not appitcable for entry into '
OPERATIONAL CONDIT0NS 2 or 3 provided the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reaching a reactor steam pressure of 600 psig and prior to entr into OPERATIONAL CONDITION 1.
- The {-A, -8, -C, -(A), -(8), -(C)" designators on the valve numbers indicate associated electrical divisions. .
.......... . . . . . . . . . - . ... . ....... ..- .. - - ..... . ..... , - m ti;; ::: t;;t hg. O., s.; ired ;M e; O thie che..e Ob; . Mil M :iitt;d t th E xt :t;; d tth "O d:,: Of th: m: f ci:=; if= 2:t r-detter.
l GRAND GULF-UNIT 1 3/4 6-30 Amenhnt No. 7, l
' e603030332 B60229 ,
PDR ADOCK 05000416
, a a
- 2. (NPE-86/01)
SUBJECT:
Technical Specification 3.7.6.2.b page 3/4 7-20 DISCUSSION: The proposed technical specification change results from a design change to install a wet pipe automatic sprinkler i system in fire zones 1A424, 1A417, and 1A428 elevation 166' - 0" of the auxiliary building. This sprinkler system will be designed and installed in accordance with NFPA 13, 1980 edition.
This design change is scheduled for implementation prior to the first refueling outage. MP&L requests NRC review and concurrence by June 1, 1986 in order to allow flexibility in the design change schedule before the first refueling outage. As done on several recent Technical Specification changes involving design changes to the plant, it is requested that the NRC issue the change with an open effective date and require that MP&L notify the NRC within 30 days of the effective date of implementation of the affected technical specification changes.
1 JUSTIFICATION: The setdown area (Fire Zone IA424) will be used to store combustibles during refueling operations. This creates a potential for a fire during refueling that could damage cables associated with Division 11 safe shutdown components. Fire Zone IA424 is located west of Fire Zone
- 1A417 and North of Fire Zone IA428. Both Fire Zones IA417 and 1A428 contain Division I and II safe shutdown components and are separated from each other by Fire Zone 1A424. With the potential to store high volumes of combustibles in Fire Zone IA424 during refueling, a postulated fire originating in this area could affect, or propagate to affect more than one train of safe shutdown.
This area contains no redundant safe shutdown-related raceways but does contain safety-related cable.e Fire protection features consisting of ionization smoke detectors, accessibility to manual hose streams, and portable fire extinguishers are provided for this area. The ionization smoke detection system alarms both locally and in the control room assuring prompt notification of plant personnel.
Following discussions with the NRC staff, MP&L committed in a July 16, 1982 letter to Mr. Harold R. Denton from L. F.
Dale to install automatic sprinkler coverage in Fire Zone IA424 prior to the commencement of the first regularly scheduled refueling outage. The proposed change is being submitted to satisfy the above commitment. Included with this change, is a drawing showing the area to be covered by the Sprinkler System, which will include coverage into areas IA417 and 1A428. 1 J12PMI86021701 - 2
r .
-}
. a SIGNIFICANT HAZARDS CONSIDERATION:
The design change associated with this proposed technical specification change will provide increased fire protection for area 1A424. Following installation, this change will reduce the potential for damage to electrical cables of safe shutdown systems.
The proposed change does not involve a significant increase in the probability or consequencts of an accident previously evaluated because it adds improvements not currently listed in the technical specifications. The potential or probability of fire damage to electrical cables of safe shutdown systems in the adjacent areas to 1A424 will be reduced by this proposed change and thus will further mitigate consequences of a fire related accident initiating from this area.
The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. This change is being proposed to .
reduce the possible effects of fire related accidents and does not create the possibility of any new or different kind of accident from those presently analyzed. The piping meets all applicable code requirements. The supports have been seismically analyzed for II/I concerns. No new failure modes are created.
The proposed change does not involve a significant reduction in the margin of safety because with the addition of the sprinkler system, the margin of safety involving fire protection of cables associated eith Division II is increased.
In its guidance on applying the criteria of 10CFR50.92(c),
the Commission stated that amendments adding requirements not listed in the technical specifications, would not involve s12 nificant hazards consideration. [48 FED. REG.
14864, 14870 (1983)] The proposed change falls int- this category and therefore involves no significant hazards consideration.
J12pMI86021701 - 3
PLANT SYSTEMS SPRAY AND/0R SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.6.2 The [ollowing spray / sprinkler systems shall be OPERABLE:
- a. Diesel Generator Building
- 1. Diesel Generator A pre-action sprinkler system N1P64D142A Diesel Generator B pre-action sprinkler system N1P6401428 2.
Diesel Generator C pre-action sprinkler system N1P640142C 3.
- b. Auxiliary Building
- 1. Elevation 93'/103' Northeast Corridor N1P640151
- 2. Elevation 119' Northeast Corridor N1P640152
- 3. Elevation 139' Northeast Corridor N1P64D153
- 4. Elevation 166' Northeast Corridor Elevation 119' West Corridor N19640158 5.
Elevation 139' West Corridor N1P64D159 6.
- 7. Elemtion 166 Northwest Corridor 8
WiP6fD162. l
- c. Control Building
- Elevation 148' Lower Cable Room N1P64D154 1.
Elevation 189' Upper Cable Room N1P640155 2.
- 3. Elevation 93' NSP640140 Fire Pump House
APPLICABILITY: Whenever equipment protected by the spray / sprinkler systems is required to be OPERABLE.
ACTION:
- a. With one or more of the above required spray and/or sprinkler systems inoperable, within one hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol.
- b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
SilRVEILLANCE REQUIREMENTS 4.7.6.2 The above required spray and sprinkler systems shall be demonstrated OPERABLE:
- a. At least once per 31 days by verifying that each valve, manual, power operated or automatic, in the flow path is in its correct position.
" Wet pipe sprinkler system.
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