Similar Documents at Perry |
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Category:TECHNICAL SPECIFICATIONS
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1999-09-09
[Table view]
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216E4791999-09-0909 September 1999
Proposed Tech Specs Revising Allowable Values for CST Low Water Level Limits from Greater than or Equal to 59,700 Gallons to Greater than or Equal to 90,300 Gallons
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ML20210M7851999-08-0404 August 1999
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Simulator Four Yr Test Rept
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Proposed Tech Specs SRs Implementing 24-month Operating Cycle at Pnpp
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Preliminary Rev 0 to Wps 01-43-T-801, Preliminary Weld Procedure for Perry Nuclear Power Plant Feedwater Nozzle Repair
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Proposed Tech Specs,Correcting Typos Found in Table 3.3.6.1-1
ML20207K1041999-03-0404 March 1999
Proposed Tech Specs Improving Licensing & Design Basis for Isolation of FW Penetrations
ML20206Q3571999-01-0606 January 1999
Proposed Tech Specs Improving Licensing & Design Basis for Isolation of Feedwater Penetrations
ML20195H5381998-11-18018 November 1998
Rev 4 to Pump & Valve Inservice Testing Program Plan
ML20155D9431998-10-27027 October 1998
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ML20155D8241998-10-27027 October 1998
Proposed Tech Specs Adding Two Paragraphs to TS 5.2.2.e, Organization - Unit Staff
ML20196H5131998-10-0808 October 1998
Rev 4,Vol 1 to Inservice Exam Program for Perry Nuclear Power Plant
ML20151V4831998-09-0909 September 1998
Proposed Tech Specs Stipulating That Water Leakage from Feedwater motor-operated CIVs Will Be Added Into Primary Coolant Sources Outside of Containment Program & Check Valves Do Not Need to Be Included in Hydrostatic Program
ML20151V1111998-09-0303 September 1998
Proposed Tech Specs Permitting EDG TS Action Completion Time of Up to 14 Days for Div 1 or 2 EDG & Allowing Performance of EDG 24-hour TS SR Test in Modes 1 & 2
ML20151V6861998-09-0303 September 1998
Proposed Tech Specs Increasing Present Div 3 DG Fuel Oil Level Requirements to Account for Rounding Error in Calculation & Unusable Volume Due to Vortex Formation at Eductor Nozzles Located in Fuel Oil Storage Tank
PY-CEI-NRR-2395, Rev 5 to Perry NPP Odcm. with1998-09-0202 September 1998
Rev 5 to Perry NPP Odcm. with
ML20151S9561998-08-31031 August 1998
Proposed Tech Specs,Allowing Blind Flange in Inclined Fuel Transfer Sys (Ifts) Containment Penetration to Be Removed While Primary Containment Is Required to Be Operable
ML20236T7911998-07-22022 July 1998
Proposed Tech Specs Revising MSL Leakage Requirements & Eliminating Msli Valve Leakage Control Sys
ML20151P1921998-07-13013 July 1998
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ML20236H8411998-06-30030 June 1998
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ML20236T8451998-06-24024 June 1998
Rev 3,Change 3 to Vol 1 of Inservice Examination Program, for Pnpp
ML20216H9361998-04-14014 April 1998
Rev 1 to Proposed TS Bases,Reflecting Changes Made Since Original Implementation of TS in Improved Format in June 1996
ML20203G4781998-02-23023 February 1998
Maint Progress Review for Perry Nuclear Power Plant
ML20197F7871997-12-23023 December 1997
Proposed Tech Specs,Revising 3.8.1 Re AC Sources to Be Consistent W/Recommendations in GL 94-01, Removal of Accelerated Testing & Special Reporting Requirements for Edgs
ML20217K6501997-10-22022 October 1997
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ML20217F5911997-10-0202 October 1997
Proposed Tech Specs,Adding Note to TS 2.1.1.2 Re MCPR SL Values & Adding Footnote to TS 5.6.5.b to Reference NRC SER That Approved MCPR SL Values for Cycle 7
ML20210T9631997-09-0808 September 1997
Proposed Tech Specs 5.2.2.e,removing Reference to NRC Policy Statement on Working Hours.Rev Allows Changes to Specific Overtime Limits & Working Hours to Be Evaluated IAW 10CFR50.59, Changes,Tests & Experiments
ML20210U8701997-09-0808 September 1997
Rev 3,change 2 to Vol 1 of Inservice Exam Program, for Pnpp
ML20217Q4591997-08-28028 August 1997
Proposed Tech Specs 3.4.11,revising Pressure-Temp Limits,Per Reactor Vessel Matl Surveillance Program Requirements Contained in App H of 10CFR50.90
ML20148A6871997-05-0202 May 1997
Proposed Tech Specs Re Surveillance Requirement for MSIV Leakage Rate Acceptance Criteria
ML20148A6591997-05-0202 May 1997
Proposed Tech Specs,Revising Existing Exception to LCO 3.0.4 as Applies to LCO 3.6.1.9 for MSIV Leakage Control Sys
ML20137S7761997-04-0909 April 1997
Proposed TS Requirements 3.9.1.1 & 3.9.2.2 Re Frequency on Refueling Equipment & one-rod-out Interlocks
ML20134D8251997-01-31031 January 1997
Proposed Tech Specs 1.1 Re definitions,3.6.1.1 Re Primary Containment - operating,3.6.1.2 Re Primary Containment Air locks,3.6.1.3 Re PCIVs,3.6.5.1 Re Drywell & 5.5 Re Programs & Manuals
ML20147B8271997-01-24024 January 1997
Rev 3 to Vol 1 of Inservice Exam Program
ML20134D8751996-10-24024 October 1996
Proposed Tech Specs 2.1.1.2,safety Limits Applying Conservatism by Increasing MCPR Safety Limit Values
ML20117E7891996-08-27027 August 1996
Proposed Tech Specs,Revising Mls Leakage Requirements & Eliminating MSIV Control Sys
ML20108A2581996-04-26026 April 1996
Proposed Improved Tech Specs
ML20100N9501996-03-0101 March 1996
Proposed TS Pages Re Drywell Leak Rate Testing Requirements
ML20100L3331996-02-27027 February 1996
Proposed Tech Specs Re Drywell Personnel Air Lock Shield Door Analyses
ML20100J5971996-02-24024 February 1996
Proposed Tech Specs,Revising Definition of Core Alteration
ML20149K2221996-02-17017 February 1996
Proposed Tech Specs,Reflecting Mod of Leakage Rate Requirements for Main Steam Lines Until End of Operating Cycle 6
ML20100G0161996-02-0101 February 1996
Draft Rev 0 to Pnpp NUMARC/NESP-007 Plant-Specific EAL Guidelines
ML20096D4651996-01-16016 January 1996
Proposed TS Requirements for Drywell Leak Rate Testing
ML20096C0591996-01-10010 January 1996
Proposed Tech Specs,Requesting one-time Surveillance Interval Extension to Support Current Schedule for Refueling Outage 5,scheduled to Begin 960127
ML20095H4721995-12-20020 December 1995
Proposed Tech Specs Re Replacement of Selected Analog Leak Detection Sys Instruments W/Ge Numac Leak Detection Monitor
ML20108B2851995-11-22022 November 1995
Rev 5 to Offsite Dose Calculation Manual
ML20094F2051995-11-0202 November 1995
Proposed Tech Specs for Handling Irradiated Fuel in Containment or Fuel Handling Bldg & Performing Core Alterations
ML20094E6751995-11-0202 November 1995
Proposed Tech Spec,Requesting Rev to TS for Onsite Power Distribution Sys:Ts 3/4.8.3.1, Distribution - Operation
1999-09-09
[Table view] |
Text
_ - _ _ _ ____
. PY-CEI/NRR-1663 L
- Attachment 1
. Page 1 of 1
. RESTATEMENT OF THE SUPPRESSION POOL AND CONTAINMENT AIR TEMPERATURE TECHNICAL SPECIFICATION AND BASES CHANGES Page Specification and Description of Changes 3.6.1.7 - Primary Containment Average Air Temperature 3/4 6-11 In the LCO and the Action, increase the primary containment average air temperature value from 90 to 95'F.
3.6.3.1 - Depressurization Systems: Suppression Pool 3/4 6-22 In the LCO, item 3.6.3.1.b, increase the maximum average
- suppression pool temperature from 90 to 95'F.
In Actions 3.6.3.1.b, 3.6.3.1.b.1 and 3.6.3.1.b.2.a, increase the maximum average suppression pool temperature from 90 to 95'F.
3/4 6-23 In Surveillance Requirements 4.6.3.1.b, 4.6.3.1.b.2, and 4.6.3.1.b.3 and 4.6.3.1.c, increase the maximum average 3/4 6-24 suppression pool temperature from 90 to 95'F.
The above Specification changes are identical to those proposed in Attachment 2, Page 2, of letter PY-CEI/NRR-1510 L. Only the temperature related changes for the Containment Air and Suppression Pool Water are listed above.
l 9306290024 930621 PDR ADOCK 05000440 P PDR
PY-CEI/NRR-1663 L Attachment 2 Table 1 Page 1 of 4 SECTIONS OF THE CONTAINMENT RESPONSE ANALYSIS TECHNICAL SPECIFICATION AMENDMENT REQUEST THAT ARE APPLICABLE TO AN INCREASE IN CONTAINMENT AIR AND SUPPRESSION POOL VATER TEMPERATURE Section of Containment Response Analysis Letter PY-CEI/NRR-1510L Applicability Clarifications Cover Letter Yes Limited to suppression pool (SP) and containment air temperature related changes.
Introduction Yes ---- ----
Summary Yes References to upper containment pool (UCP) changes, SP level changes, and peak accident pressure (P ) changes are not applicable.
Refer to the listing of the TS changes in this letter (Attachment 1, page 1 of 1).
- Reasons for the Change Yes ---- ----
Background Yes ---- ----
- Safety Analysis - Part A: Yes References to UCP changes, SP level and peak Containment Response Analysis P, changes are not applicable.
A.1 Inputs to the Containment Yes ---- ----
Response Analysis Increased SP Vater & Yes ---- ----
Containment Air Temperature
- Expandad SP Water Level No ----
Operating Band Dryvell-to-Containment dp No ---- ----
Assumed Higher Rx Power Level Yes Increases conservatism.
9 D
PY-CEI/NRR-1663 L i Attachment 2 Table 1 '
Page 2 of 4
- UCP Vater Level and Temperature No ---- ----
A.2 Short-Term Containment Response Yes Increased conservatism. i A.3 Long-Term (LT) Containment Yes Increased conservatism.
Response
- Event Response for the LT Yes Increased conservatism. '
Analysis
- SP Dravdown Event Analysis No ----
A.4 Dryvell Negative Pressure Yes ---- ----
Response ,
- A.5 Containment Leakage Testing No ----
Safety Analysis - Part B: Yes References to the UCP changes are not ,
Contai.. ment Structural and applicable.
Hydrodynamic Response
- B.1 S t ruc tu ra.1 Design Review- Yes ---- ----
B.2 LOCA Related Containment Loads Yes References to SP level changes are'not applicable. -;
- 1. LOCA Bubble & Pool Svell Yes References to SP level changes are not Loads applicable.
- 2. Condensation Oscillation- Yes References to SP level change's are'not Loads applicable. ,
t
- 3. Chugging Yes . References to SP level changes are not applicable.
B.3 SRV Operational Loads Yes References to SP level changes are not applicable.
D
_ _ _ _ . _ _ .- .._.._.____________m _ _ _ . - _ _ _ _ . _ ______a = _. __=i,- -_.--e. . . _ . _ _ -- -
_ __ +- _ue _ _ _ _ _ _ _ _ _ _ . _ . _ _ _
-.__m-_
i PY-CEI/NRR-1663 L Attachment 2 Table 1 Page 3 of 4
- 1. Air-Clearing Loads Yes References to SP level changes are not applicable.
- 2. Steam Condensation Loads Yes References to SP level changes and UCP changes are not applicable.
Safety Analysis - Part C: Yes Plant-Specific Considerations C.1 NPSH Yes References to SP level changes are not applicable.
C.2 ECCS Pump Seal Integrity Yes ----
- C.3 Core. cooling capability Yes C.4 Impact on the E0Ps Yes References to SP level changes and UCP changes are not applicable.
C.5 SB0 Yes References to SP level changes and UCP changes are not applicable.
i C.6 ATVS Yes References to SP level changes and UCP changes
- are not anplicable.
C.7 Fire Hazards Analysis Yes ----
C.8 Submergence of SP Temperature No SP vater levels are unchanged.
Monitors i
4 -
C.9 EQ Yes ----
1 - C.10 Hydrogen Control Analysis Yes ----
S'ummary of All the Parts Yes References to UCP changes,.SP level changes, Conclusions and peak Pa changes in-the summary paragraph are not applicable.
4 e 4
7 n
_ _ _. _ . . . . _. . ._-._.__...__,._.m _ __ _ _ _ . . _ _ . ._ . _ _ _ _ . . . _ . _ . _ . . . . _ . _ _ _ _.m.. . _ . .
PY-CEI/NRR-1663 L Attachment 2 Table 1 Page 4 of 4 Significant Hazards Consideration Yes ---- ----
I. Containment Response Input, Yes References to UCP changes, SP level Structural and Plant-Specific level changes, and peak P, changes are not Considerations applicable.
II. Containment Response No ----
Analysis - P 3 - III. Reduction in UCP Depth - No ---- ----
Refueling IV. Editorial Changes No ---- ----
Environmental Consideratior. Yes ---- ----
References Yes ---- ----
- Table 1: Containment Response Yes References to UCP changes, SP level changes Input Parameters and Event Results and peak P changes are not applicable.
Figure 1: SP. Level Adjustment No ----
Graph
- Attachment.2: Listing of the Yes Use the portions of the listing for Proposed TS and Bases Changes temperature changes to Specifications 3.6.1.7 and 3.6.3.1 (pages 3/4 6-11, 3/4 6-22, 3/4 6-23, and 3/4 6-24).
- Attachment 3: TS Mark-up Pages Yes Only revising Specifications 3.6.1.7 and 3.6.3.1 to reflect increased temperatures.
l
- GE Containment Response Analysis Yes Full capability of analysis not utilized Report through issuance of this limited scope amendment.
4 8 g
~
i .
A J
___m _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ .
