Proposed Tech Specs Replacement Bases Pages Associated W/Proposed Amend to License Re Response Time TestingML20211M848 |
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Grand Gulf ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
10/06/1997 |
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From: |
ENTERGY OPERATIONS, INC. |
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To: |
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Shared Package |
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ML20211M846 |
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References |
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NUDOCS 9710150162 |
Download: ML20211M848 (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] |
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RPS Instrumentation B 3.3.1.1 j BASES SURVEILLANCE $R 3.3.1.1.15 REQUIREMENTS (continued)
This SR ensures that the individual channel response times are less than accident or equal to the maximum values assumed in the analysis.
The RPS RESPONSE TIME acceptance criteria are included in the applicable plant procedures.
As noted, neutron detectors are excluded from RPS RESPONSE TIME testing because the principles of detector o virtually ensure an instantaneous response time. peration Note 2 allows the channel sensors of Functions 3, 4, and 5 to be excluded from specific RPS RESPONSE TIME testing. This allowance to not perform specific response time testing of the sensors is applicable when the alternate testing requirements and restrictions of Reference 10 are performed.
As stated in Reference 10, analysis has demonstrated that other Technical Specification testing requirements (CHANNEL CALIBRATIONS, CHANNEL CHECKS, CHANNEL FUNCTIONAL TESTS, a LOGIC SYSTEM FUNCTIONAL TESTS) and actions taken in response to NRC Bulletin 90-01 Supplement I are sufficient to identify failure modes or degradation in instrument response within acceptable limits. times and assure operation of the analyze Reference 10 also identifies that there are no known channel sensor failure modes identified that can be detected by Technical Specification required surveillances. Therefore, response time when the requirements, including sensor types, of Reference 10 are complied with, adequate assurance of the response time of the sensors is provided.
This assurance of the time testing of the remainder of the channel ensures tha the individual channel response times are less than er equal to the maximum values assumed in the accident analysis.The calibration shall be performed such that fast ramp or step 1
change to system components during calibrations is performed change is prompt.to verify that the response of the transmitter to the i time degradation during the performance of calibrations. Tech Technicians shall be appropriately trained to en.ture they are aware of the consequences of instrument response time degradation.
- 11. These items are commitments made per Reference If the alternate testing requirements of Reference 10 are not complied with, then the entire channel will be response time tested including the sensors.
. (continued)
GRAND GULF B 3.3-29 LOC 97078 9710150162 PDR 971006 P ADOCK 05000416 PDR
RPS Instrumeatation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.15 (continued)
REQUIREMENTS RPS RESPONSE TIME tests are conducted on an 18 month STAGGERED TEST BASIS. Note 3 requires STAGGERED TEST BASIS I Frequency to be determined based on 4 channels per trip system, in lieu of the 8 channels specified in Table 3.3.1.1-1 for the MSIV Closure Function. This Frequency is based on the logic interrelationships of the various channels required to produce an RPS scram signal.
Therefore, staggered testing results in response time verification of these devices every 18 months. This Frequency is consistent with the typical industry refueling cycle and is based upon plant operating experience, which shows that random failures of instrumentation components causing serious time degradation, but not channel Failure, are infrequent.
1 REFERENCES 1. UFSAR, Figure 7.2-1.
I 2. UFSAR, Section 5.2.2.
l
- 3. UFSAR, Section 6.3.3.
- 4. UFSAR, Chapter 15.
- 5. UFSAR, Section 15.4.1.
- 6. NED0-23842, " Continuous Control Rod Withdrawal in the Startup Range,' April 18, 1978.
- 7. UFSAR, Section 15.4.9.
(continued)
GRAND GULF B 3.3-29a LDC 97078 o
RPS Instrumentation B 3.3.1.1 BASES REFERENCES 8. Letter, P. Check (NRC) to G. Lainas (NRC), "BWR (continued) Scram Discharge System Safety Evaluation,"
December ', 1980, as attached to NRC Generic Letter dated December 9, 1980.
- 9. NED0 30851-P-A, " Technical Specification improvement Analyses for BWR Reactor Protection System,"
March 1988.
- 10. NEDO-32291-A, " System Analyses for Elimination of Selected Response Time Testing Requirements," October 1995,
- 11. GNRI-97/000__, Amendment 133 to the Operating License.
t GRAND GULF B 3.3-30 LDC 97078 o
+. ..
. Pricary Containment and Drywell Isolation Instrumentation B 3.3.6.1 BA$ES w
SURVEILLANCE SR 3.3.6.1.7 REQUIREMENTS (continued) The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required isolation logic for a specific channel. The system functional testing performed on isolation valves in LC0 3.6.1.3 and LCO 3.6.5.3 overlaps this !"rveillance to provide complete testing of the assumed safety function. The 18 month Frequency is based on the '
need to perform this Surveillance under the conditions that apply during a plant outage arid the potential for an unplanned transient if the Surveillance were performed with the reactor at power.
Operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency.
SR 3.3.6.1.8 This SR ensures that the individual channel response times are less than or equal to the maximum values assumed in the accident analysis. Testing is performed only on channels where the assumed response time does not correspond to the I
diesel generator (DG) start time. For channels assumed to respond within the DG start time, sufficient margin exists in the 10 second start time when compared to the typical channel response time (milliseconds) so as to assure adequate response without a specific measurement test.
Testing of the closure times of the MSIVs is not included in this Surveillance since the closure time of the MSIVs is tested by SR 3.6.1.3.6. ISOLATION SYSTEM RESPCNSE TIME acceptance criteria for this instrumentation is included in the applicable plant procedures.
As Noted, the channel sensor may be excluded from response time testin~g. This allowance to not perform specific response time testing of the sensors is applicable when the alternate testing requirements and restrictions of Reference 7 are performed. As stated in Reference 7. analysis has demonstrated that other Technical Specification testing l requirements (CHANNEL CALIBRATIONS, CHANNEL CHECKS, CHANNEL 1 FUNCTIONAL TESTS, and LOGIC SYSTEM FUNCTIONAL TESTS) and <
actions taken'in response to NRC Bulletin 90-01 Supplement 1 are sufficient to identify failure modes or degradation in (continued) .
GRAND GULF B 3.3-170 LOC 97078
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Primary Containment and Drywell isolation instrumentation B 3.3.6.1 BASES SURVEILLANCE SR 3.3.6.1.8 (continued)
REQUIREMENTS instrument response times and assure ooeration of the analyzed instrument loops within acceptable limits.
Reference 7 also identifies that there are no known channel sensor failure modes identified that can be detected by response time testing that cannot also L> detected by other Tec1nical Specification required surveillances. Therefore, when the requirements, including sensor types, of Reference 7 are complied with, adequate assurance of the response time of the sensurs is provided. This assurance of the response i time of the sensors when combined with the response time testing of the remainder of the channel ensures that the l individual channel response times are less than or equal to the maximum values assumed in the a.cident analysis. The calibration shall be performed suct that fast ramp or step change to system components during calibrations is aerformed toverifythattheresponseofthetransmittertot1einput change is prompt. Tecnnicians shall monitor for response time degradation during the performance of calibrations.
l- Technicians shall be appropriately trained to ensure they l
are aware of the consequences of instrument response time degradation. These items are commitments made per Reference
- 8. If the alternate testing requirements of Reference 7 are not complied with then the entire channel will be response time tested including the sensors.
ISOLATION SYSTEM RESPONSE TIME tests for this instrumentation are conducted on an 18 month STAGGERED TEST BASIS. This test Frequency is consistent with the typical industry refueling cycle and is based upon plant operating experience that shows that random failures of instrumentation components causing serious response time degradation, but not channel failure, are infregunt.
REFERENCES 1. UFSAR, Chapter 6,
- 2. UFSAR, Chapter 15.
l (continued)
GRAND GULF B 3.3 170a LDC 97078
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Pricary Containment and Drywell isolation Instrumentation B 3.3.6.1 BASES REFERENCES 3. NE00 31466, " Technical Specification Screening (continued) Criteria Application and Risk Assessment,"
November 1987
- 4. UFSAR, Section 9.3.5.
- 5. NEDC 31677 P A. " Technical Specification improvement i Analysis for BWR isolation Actuation instrumentation,"
June 1989.
- 6. NEDC 30851 P A, Supplement 2. " Technical Specifications improvement Analysis for BWR isolation Instrumentation Common to RPS and ECCS Instrumentation," March 1989.
- 7. NED0 32291 A, " System Analyses for Elimination of Selected Response Time Testing Requirements," October 1995.
- 8. GNRI 97/000_ , Amendment 133 to the Operating License.
4 GRtND GULF B 3.3 171 LOC 97078
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