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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20209H5051999-07-14014 July 1999 Proposed Tech Specs Pages 3.1-15 & 3.1-17 of Table 3.1.1 ML20209E0951999-07-0707 July 1999 Proposed Tech Specs,Changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20212H5441999-06-18018 June 1999 Proposed Tech Specs Reflecting Installation of Addl SFP Storage Racks That Will Accommodate Increase in Spent Fuel Assemblies Beyond Existing Storage Capacity of SFP as Described in Licensing Rept ML20195D0761999-06-0303 June 1999 Proposed Tech Specs,Permitting Plant Operation with Three Operable Recirculation Loops ML20205P8531999-04-15015 April 1999 Proposed Tech Specs,Modifying Number of Items in Sections 2 & 3 of Tss,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4 ML20198K0671998-12-23023 December 1998 Proposed Tech Specs Pages 3.8-2 & 4.8-1,changed to Specify Surveillance Frequency of Once Per Three Months ML20195C6561998-11-10010 November 1998 Proposed Tech Specs Section 5.1.A,removing Restriction on Sale or Lease of Property within Exclusion Area ML20155J7501998-11-0505 November 1998 Proposed Tech Specs,Modifying Safety Limits & Surveillances of LPRM & APRM Sys & Related Bases to Ensure APRM Channels Respond within Necessary Range & Accuracy & to Verify Channel Operability ML20151V5091998-09-0303 September 1998 Proposed Tech Specs 3.4.A.10.e & 3.5.A.2.e Re Condensate Storage Tank Level ML20237D9591998-08-21021 August 1998 Proposed Tech Specs Removing Requirement for ADS Function of EMRV to Be Operable During Rv Pressure Testing & Correcting Note H of Table 3.1.1 ML20237B2221998-08-0606 August 1998 Proposed Revised Tech Specs Pages for Change Request 205,dtd 961031,correcting Minor & Inadvertent Editorial Changes in Locations Where Changes Have Not Been Proposed ML20236T1211998-07-23023 July 1998 Proposed Tech Specs Pages for Amend to License DPR-16,to Establish That Existing SLMCPR Contained in TS 2.1.A Is Applicable for Next Operating Cycle (Cycle 17) ML20236T4981998-07-21021 July 1998 Proposed Tech Specs Re Reactivity Control ML20236T4811998-07-21021 July 1998 Proposed Tech Specs Re Changes to Administrative Controls ML20236J1431998-06-30030 June 1998 Proposed Tech Specs,Consisting of Revised Page 3-5 Re RPV Pressure/Temp Limits ML20236H2181998-06-29029 June 1998 Proposed Tech Specs,Modifying EDG Insp Requirement Previously Submitted in Entirety ML20248K2851998-05-28028 May 1998 Proposed Tech Specs Re That Such First Type a Test Required by Primary Containment Leakage Rate Testing Program Be Performed During Refueling Outage 18R ML20197G2771997-12-23023 December 1997 Proposed Tech Specs Reflecting Change in Trade Name of Owner & Operator of Oyster Creek Nuclear Generating Station ML20197J2561997-12-10010 December 1997 Proposed Tech Specs Changing Pages 2.3-6,2.3-7,3.1-11, 3.1-14,3.1-16,3.4-8,3.8-2,3.8-3,4.3-1,4.5-13 & 6-1 ML20210L3311997-08-15015 August 1997 Proposed Tech Specs,Incorporating Note Which Indicates That Proposed Change to SL Mcrp Applicable for Current Operating Cycle (Cycle 16) Only ML20135C2001996-11-27027 November 1996 Proposed Tech Specs Pages 4.7-1,4.7-2,4.7-3 & 4.7-4 Re Surveillances for Station Batteries ML20129K3401996-11-12012 November 1996 Proposed Tech Specs,Consisting of Change Request 224, Implementing Revised 10CFR20, Stds for Protection Against Radiation Effective 910620 ML20134H0541996-10-31031 October 1996 Proposed Tech Spec,Requesting Deletion of Table 3.5.2 ML20129C0691996-10-10010 October 1996 Proposed Tech Specs,Clarifying Functional Requirement to Provide Interlock Permissive Which Ensures Source of Cooling Water Available Via Core Spray Sys Prior to Depressurization ML20129A5731996-10-10010 October 1996 Proposed Tech Specs,Revising Addl Group of Surveillances Where Justification Completed Following Receipt of Amend 144 ML20134F4101996-10-0404 October 1996 Proposed Tech Specs 2.1.A & 3.10.C to Reflect Change in SLMCPR & Revise Operating CPR Limit for Stability, Respectively ML20117E7061996-08-23023 August 1996 Proposed Tech Specs,Proposing New pressure-temp Limits Up to 22,27 & 32 EFPY Based on Predicted Nilductility Adjusted Ref Temp for Corrresponding EFPY of Operation ML20115G2101996-07-17017 July 1996 Proposed Tech Specs,Allowing Implementation of 10CFR,App J, Option B ML20113A8641996-06-19019 June 1996 Proposed Tech Specs Table of Contents,1.24 Re Footnote to definition,1.25 Re Definition,Section 3.5.A.3b Re Containment,Section 4.5 Re Containment,Bases for Section 4.5 & Section 6.9.3.b Re Reporting Requirements ML20111A3841996-05-0707 May 1996 Proposed Tech Specs,Adopting Provisions of STS NUREG-1433, Rev 1,dtd 950407,Sections SR 3.0.1,3.0.3 & Associated Bases ML20107E7751996-04-15015 April 1996 Proposed Tech Specs 5.3.1 Re Handling Heavy Loads Over Irradiated Fuel ML20101J7681996-03-28028 March 1996 Proposed Tech Specs,Modifying Statements in TS & Bases to Correctly Reflect Ref Parameter for Anticipatory Scram Signal Bypass ML20101J6091996-03-25025 March 1996 Proposed Tech Specs,Deleting Spec Which Requires Thorough Insp of EDG Every 24 Months During Shutdown ML20100J9151996-02-23023 February 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B ML20100H9971996-02-22022 February 1996 Proposed Tech Specs 3.7-1,3.7-2,4.7-1 & 4.7-2 Re Deletion of TS Requirement to bi-annually Inspect EDG & Mod of Spec Re AOT ML20095C1031995-12-0505 December 1995 Proposed Tech Specs Re Rev of Submittal Date for Annual Exposure Data Rept Bringing Plant Into Conformance w/10CFR20.2206 & Relaxing Overly Restrictive Administrative Requirement ML20086A7161995-06-26026 June 1995 Proposed Tech Specs Re Performance of Reactor Shutdown & Drywell to Inspect Snubbers in Svc for Only 12 Months ML20080P6501995-02-28028 February 1995 Proposed Tech Specs Change Request 225 Re Change to Page 6-4 of Tech Spec Section 6.5.1.12.Change Consistent w/NUREG-1433,STSs General Electric Plants,BWR/4,Rev 0,dtd 920928 ML20078N3791995-02-0808 February 1995 Proposed Tech Specs Re Oyster Creek Spent Fuel Pool Expansion ML20078Q6481994-12-15015 December 1994 Revised TS & Bases Pages to Section 3.1 of TS Change Request 191 ML20078M1431994-11-25025 November 1994 Proposed TS 5.3.1.E,allowing 2,645 Fuel Assemblies to Be Stored in Fuel Pool ML20072S2921994-09-0202 September 1994 Proposed Tech Specs Supporting Rev of APRM Channel Calibr Interval from Weekly to Quarterly ML20072L4741994-08-19019 August 1994 Proposed Tech Specs Control Rod Exercising & Standby Liquid Control Pump Operability Testing ML20070E3411994-07-0808 July 1994 Proposed Tech Specs Re Improved Protection to Safety Related Electrical Equipment from Loss of Capability ML20078A7731994-06-24024 June 1994 Proposed Tech Specs Reflecting Removal of Recirculation Flow Scram ML20069M8231994-06-15015 June 1994 Proposed Tech Spec 2.3.D, Reactor High Pressure,Relief Valve Initiation ML20070R5261994-05-12012 May 1994 Proposed TS Sections 3.1 & 4.1 for Protective Instrumentation ML20029E0451994-05-0606 May 1994 Proposed Tech Specs Clarifying Requirements for Demonstrating Shutdown Margin ML20065M9991994-04-19019 April 1994 Proposed Tech Specs Updating & Clarifying TS 3.4.B.1 to Be Consistent W/Existing TS 1.39 & 4.3.D Re Five Electromatic Relief Valves Pressure Relief Function Inoperable or Bypassed During Sys Pressure Testing ML20029C7571994-04-15015 April 1994 Proposed TS Change Request 215,deleting Audit Program Frequency Requirements from TS 6.5.3 & Utilize Operational QA Plan as Controlling Document 1999-07-07
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212B5741999-09-0505 September 1999 Rev 11 to 2000-ADM-4532.04, Oyster Creek Emergency Offsite Dose Calculation Manual ML20209H5051999-07-14014 July 1999 Proposed Tech Specs Pages 3.1-15 & 3.1-17 of Table 3.1.1 ML20209E0951999-07-0707 July 1999 Proposed Tech Specs,Changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20212H5441999-06-18018 June 1999 Proposed Tech Specs Reflecting Installation of Addl SFP Storage Racks That Will Accommodate Increase in Spent Fuel Assemblies Beyond Existing Storage Capacity of SFP as Described in Licensing Rept ML20195D0761999-06-0303 June 1999 Proposed Tech Specs,Permitting Plant Operation with Three Operable Recirculation Loops ML20205P8531999-04-15015 April 1999 Proposed Tech Specs,Modifying Number of Items in Sections 2 & 3 of Tss,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4 ML20198K0671998-12-23023 December 1998 Proposed Tech Specs Pages 3.8-2 & 4.8-1,changed to Specify Surveillance Frequency of Once Per Three Months ML20195C6561998-11-10010 November 1998 Proposed Tech Specs Section 5.1.A,removing Restriction on Sale or Lease of Property within Exclusion Area ML20155J7501998-11-0505 November 1998 Proposed Tech Specs,Modifying Safety Limits & Surveillances of LPRM & APRM Sys & Related Bases to Ensure APRM Channels Respond within Necessary Range & Accuracy & to Verify Channel Operability ML20151V5091998-09-0303 September 1998 Proposed Tech Specs 3.4.A.10.e & 3.5.A.2.e Re Condensate Storage Tank Level ML20237D9591998-08-21021 August 1998 Proposed Tech Specs Removing Requirement for ADS Function of EMRV to Be Operable During Rv Pressure Testing & Correcting Note H of Table 3.1.1 ML20237B2221998-08-0606 August 1998 Proposed Revised Tech Specs Pages for Change Request 205,dtd 961031,correcting Minor & Inadvertent Editorial Changes in Locations Where Changes Have Not Been Proposed ML20236T1211998-07-23023 July 1998 Proposed Tech Specs Pages for Amend to License DPR-16,to Establish That Existing SLMCPR Contained in TS 2.1.A Is Applicable for Next Operating Cycle (Cycle 17) ML20236T4811998-07-21021 July 1998 Proposed Tech Specs Re Changes to Administrative Controls ML20236T4981998-07-21021 July 1998 Proposed Tech Specs Re Reactivity Control ML20236J1431998-06-30030 June 1998 Proposed Tech Specs,Consisting of Revised Page 3-5 Re RPV Pressure/Temp Limits ML20236H2181998-06-29029 June 1998 Proposed Tech Specs,Modifying EDG Insp Requirement Previously Submitted in Entirety ML20248K2851998-05-28028 May 1998 Proposed Tech Specs Re That Such First Type a Test Required by Primary Containment Leakage Rate Testing Program Be Performed During Refueling Outage 18R ML20197G2771997-12-23023 December 1997 Proposed Tech Specs Reflecting Change in Trade Name of Owner & Operator of Oyster Creek Nuclear Generating Station ML20197J2561997-12-10010 December 1997 Proposed Tech Specs Changing Pages 2.3-6,2.3-7,3.1-11, 3.1-14,3.1-16,3.4-8,3.8-2,3.8-3,4.3-1,4.5-13 & 6-1 ML20210L3311997-08-15015 August 1997 Proposed Tech Specs,Incorporating Note Which Indicates That Proposed Change to SL Mcrp Applicable for Current Operating Cycle (Cycle 16) Only ML20135C2001996-11-27027 November 1996 Proposed Tech Specs Pages 4.7-1,4.7-2,4.7-3 & 4.7-4 Re Surveillances for Station Batteries ML20129K3401996-11-12012 November 1996 Proposed Tech Specs,Consisting of Change Request 224, Implementing Revised 10CFR20, Stds for Protection Against Radiation Effective 910620 ML20134H0541996-10-31031 October 1996 Proposed Tech Spec,Requesting Deletion of Table 3.5.2 ML20129C0691996-10-10010 October 1996 Proposed Tech Specs,Clarifying Functional Requirement to Provide Interlock Permissive Which Ensures Source of Cooling Water Available Via Core Spray Sys Prior to Depressurization ML20129A5731996-10-10010 October 1996 Proposed Tech Specs,Revising Addl Group of Surveillances Where Justification Completed Following Receipt of Amend 144 ML20134F4101996-10-0404 October 1996 Proposed Tech Specs 2.1.A & 3.10.C to Reflect Change in SLMCPR & Revise Operating CPR Limit for Stability, Respectively ML20117E7061996-08-23023 August 1996 Proposed Tech Specs,Proposing New pressure-temp Limits Up to 22,27 & 32 EFPY Based on Predicted Nilductility Adjusted Ref Temp for Corrresponding EFPY of Operation ML20115G2101996-07-17017 July 1996 Proposed Tech Specs,Allowing Implementation of 10CFR,App J, Option B ML20113A8641996-06-19019 June 1996 Proposed Tech Specs Table of Contents,1.24 Re Footnote to definition,1.25 Re Definition,Section 3.5.A.3b Re Containment,Section 4.5 Re Containment,Bases for Section 4.5 & Section 6.9.3.b Re Reporting Requirements ML20111A3841996-05-0707 May 1996 Proposed Tech Specs,Adopting Provisions of STS NUREG-1433, Rev 1,dtd 950407,Sections SR 3.0.1,3.0.3 & Associated Bases ML20107E7751996-04-15015 April 1996 Proposed Tech Specs 5.3.1 Re Handling Heavy Loads Over Irradiated Fuel ML20101P1561996-03-31031 March 1996 Rev 9 to Oyster Creek Nuclear Generating Station Pump & Valve IST Program ML20101J7681996-03-28028 March 1996 Proposed Tech Specs,Modifying Statements in TS & Bases to Correctly Reflect Ref Parameter for Anticipatory Scram Signal Bypass ML20101J6091996-03-25025 March 1996 Proposed Tech Specs,Deleting Spec Which Requires Thorough Insp of EDG Every 24 Months During Shutdown ML20100J9151996-02-23023 February 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B ML20100H9971996-02-22022 February 1996 Proposed Tech Specs 3.7-1,3.7-2,4.7-1 & 4.7-2 Re Deletion of TS Requirement to bi-annually Inspect EDG & Mod of Spec Re AOT ML20095C1031995-12-0505 December 1995 Proposed Tech Specs Re Rev of Submittal Date for Annual Exposure Data Rept Bringing Plant Into Conformance w/10CFR20.2206 & Relaxing Overly Restrictive Administrative Requirement ML20086A7161995-06-26026 June 1995 Proposed Tech Specs Re Performance of Reactor Shutdown & Drywell to Inspect Snubbers in Svc for Only 12 Months ML20080P6501995-02-28028 February 1995 Proposed Tech Specs Change Request 225 Re Change to Page 6-4 of Tech Spec Section 6.5.1.12.Change Consistent w/NUREG-1433,STSs General Electric Plants,BWR/4,Rev 0,dtd 920928 ML20078N3791995-02-0808 February 1995 Proposed Tech Specs Re Oyster Creek Spent Fuel Pool Expansion ML20078Q6481994-12-15015 December 1994 Revised TS & Bases Pages to Section 3.1 of TS Change Request 191 ML20078M1431994-11-25025 November 1994 Proposed TS 5.3.1.E,allowing 2,645 Fuel Assemblies to Be Stored in Fuel Pool ML20073F9501994-09-26026 September 1994 Revised Plan for Long Range Planning Program for Oyster Creek Nuclear Generating Station ML20073F9411994-09-26026 September 1994 Revised Plan for Long Range Planning Program for TMI Nuclear Station Unit 1 ML20072S2921994-09-0202 September 1994 Proposed Tech Specs Supporting Rev of APRM Channel Calibr Interval from Weekly to Quarterly ML20072Q4251994-08-20020 August 1994 Rev 0 to Oyster Creek Nuclear Generating Station Sea Turtle Surveillance,Handling & Reporting Instructions for Operations Personnel ML20072L4741994-08-19019 August 1994 Proposed Tech Specs Control Rod Exercising & Standby Liquid Control Pump Operability Testing ML20070J7971994-07-31031 July 1994 Rev 8 to Oyster Creek Nuclear Generating Station Pump & Valve Inservice Testing Program ML20070E3411994-07-0808 July 1994 Proposed Tech Specs Re Improved Protection to Safety Related Electrical Equipment from Loss of Capability 1999-09-05
[Table view] |
Text
9 ATTACHMENT PROPOSED CHANGE PRESSURE-TEMPERATURE RELATIONSHIP APPENDIX A TO PROVISIONAL OPERATING LICENSE DPR-16 OYSTER CREEK NUCLEAR GENERATING STATION GPU NUCLEAR CORPORATION DOCKET NO. 50-219 P
3.3 REACTOR COOLANT Applicability: Applies to the operating status of the reactor coolant system.
Obiective: To assure the stmeture integrity of the reactor coolant system.
Specification: A. Pressure Temperature Relationships I
(i) Reactor Vessel Pressure Tests - the minimum reactor vessel temperature at a given pressure shall be in excess of that indicated by the curve A in Figures 3.3.1,3.3.2 and 3.3.3 for reactor operations to '
22, 27 and 32 effective full power years, respectively. The maximum
- temperature for Reactor Vessel Pressure Testing is 250 F.
- (ii) Heatup and Cooldown Operations
- Reactor noncritical -- the minimum reactor vessel temperature for heatup and cooldown j operations at a given pressure when the reactor is not critical shall be in excess of that indicated by the curve B in Figures 3.3.1, 3.3.2 and
, 3.3.3 for reactor operations up to 22,27 and 32 effective full power years, respectively.
(iii) Power operations -- the minimum reactor vessel temperature for power operations at a given pressure shall be in excess of that indicated by the curve C in Figure 3.3.1,3.3.2 and 3.3.3 for reactor operations up to 22,27 and 32 effective full power years respectively.
Note: Curves A, B and C in Figures 3.3.1,3.3.2 and 3.3.3 apply when the closure head is on the reactor vessel and studs are fully tensioned.
(iv) Appropriate new pressure temperature limits must be generated when the reactor system has reached thirty two (32) effective full power years of reactor operation.
B. Reactor Vessel Closure Head Boltdown: The reactor vessel closure head studs may be elongated .020" (1/3 design preload) with no restrictions on reactor vessel temperature as long as the reactor vessel is at atmospheric pressure. Full tensioning of the studs is not permitted unless the temperature of the reactor vessel flange and closure head flange is in excess of 85 F.
C. Thermal Transients
- 1. The average rate of reactor coolant temperature change during normal heatup and cooldown shall not exceed 100 F in any one hour period.
- 2. The pump in an idle recirculation loop shall not be started unless the temperature of the coolant within the idle recirculation loop is within 50 F of the reactor coolant temperature.
OYSTER CREEK 3.3-1 Amendment No: 42,120,151
Transformation temperature. The minimum temperature for pressurization at any time in life has to account for the toughness propcrties in the most limiting regions of the reactor vessel, as well as the effects of fast neutron embrittlement.
Curves A, B and C on Figures 3.3.1,3.3.2 and 3.3.3 are derived from an evaluation of the !
fracture toughness properties performed on the specimens coritained in Reactor Vessel :
Materials Surveillance Program Capsule No. 2 (Reference 14). The results of dosimeter !
wire analyses (Reference 14) indicated that the neutron fluence (E>l.0 MeV) at the end of 2
32 effective full power years of operation is 2.36 x 10" n/cm at the 1/4T (T= vessel wall thickness) location. This value was used in the calculation of the adjusted reference !
nil-ductility temperature which, in turn, was used to generate the pressure-temperature i curves A, B and C on Figures 3.3.1,3.3.2 and 3.3.3 (Reference 15). The 250 F maximum pressure test temperature provides ample margin against violation of the minimum i required temperature. Secondary containment is not jeopardized by a steam leak during ,
pressure testing, and the Standby Gas Treatment system is adequate to prevent unfiltered release to the stack.
l li Stud tensioning is considered significant from the standpoint of brittle fracture only when f the preload exceed approximately 1/3 of the final design value. No vessel or closure stud j minimum temperature requirements are considered necessary for preload values below 1/3 of the design preload with the vessel depressurized since preloads below 1/3 of the design i preload result in vessel closure and average bolt stresses which are less than 20% of the 1 yield strengths of the vessel and bolting materials. Extensive service experience with these ;
materials has confirmed that the probability of brittle fracture is extremely remote at these low stress levels, inespective of the metal temperature.
l The reactor vessel head flange and the vessel flange in combination with the double "O" l ring type seal are designed to provide a leak tight seal when bolted together. When the !
vessel head is placed on the reactor vessel, only that portion of the head flange near the i inside of the vessel rests on the vessel flange. As the head bolts are replaced and tensioned, the vessel head is flexed slightly to bring together the entire contact surface adjacent to the "O" rings of the head and vessel flange. The original Code requirement was that boltup be done at qualification temperatures (T3OL) plus 60 F. Current Code requirements state (Ref.16) that for application of full bolt preload and reactor pressure up to 20% of hydrostatic test pressure, the RPV metal temperature must be at RTer or greater. The boltup temperature of 85 F was derived by determining the highest value of (T3OL + 60) and the highest value of RTmr, and by choosing the more conservative value of the two. Calculated values of(T3OL + 60) and RTmr of the RPV metal temperature were 85 F and 36 F, respectively (Ref.15). Therefore, selecting the boltup temperature to be 85 F provides 49 F margin over the current Code requirement based on j RTmr. ;
Detailed stress analyses (4) were made on the reactor vessel for both steady state and transient conditions with respect to material fatigue. The results of these analyses are presented and compared to allowable stress limits in Reference (4). The specific conditions analyzed included 120 cycles of normal startup and shutdown with a heating and cooling rate of 100 F per hour applied continuously over a temperature range of ;
100 F to 546 F and for 10 cycles of emergency cooldown at a rate of 300 F per hour I applied over the same range. Thermal stresses from this analysis combined with the I primary load OYSTER CREEK 3.3-5 Amendment No: 15,42,120,151 j
References:
(1) FDSAR, Volume I, Section IV-2 (2) Letter to NRC dated May 19,1979, " Transient of May 2,1979" ,
(3) General Electric Co. Letter G-EN-9-55, " Revised Natural Circulation Flow Calculation", dated May 29,1979 (4) Licensing Application Amendment 16, Design Requirements Section (5) (Deleted) i (6) FDSAR, Volume 1, Section IV-2.3.3 and Volume II, Appendix H
~
-(7) FDSAR, Volume I, Table IV-2-1 (8) Licensing Application Amendment 34, Question 14 (9) Licensing Application Amendment 28, item III-B-2 l' (10) Licensing Application Amendment 32, Question 15 (11) (Deleted) ,
(12) (Deleted)
(13) Licensing Application Amendment 16, Page 1 :
(14) GPUN TDR 725 Rev. 3: Testing and Evaluation of Irradiated Reactor Vessel Materials Surveillance Program Specimens (15) GENE-B13-01769 (GE Nuclear Energy): Pressure-Temperature Curves Per Regulatory Guide 1,99, Revision 2 for Oyster -
Creek Nuclear Generating Station. ,
(16) Paragraph G-2222(C), Appendix G,Section XI, ASME Boiler and Pressure Vessel Code,1989 Edition with 1989 Addenda, ;
" Fracture Toughness Criteria for Protection Against Failure."
i l
l l
l l
OYSTER CREEK 3.3-8a Amendment No: 135,140,151 I
1 FIGURE 3.3.1 l
OYSTER CREEK P-T CURVES VALID TO 22 EFPY l
1600 i i
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22 ,
l swv 8 C 1400 p , 7 l
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3 1200 G
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' 4.
o 1000 ,
dm ; x l I CORE BELTUNE LIMITS I
E j l $ 800 f WITH ART OF 145'F FoR LOWER SHELL l y PLATE G-8-6 j w
l g A - SYSTEM HYOROTEST LIMIT I w WITH FUEL IN VESSEL l l ! 600 g B NON. NUCLEAR HEATUF/
[, 560 psig l
s ;
f CootcowN UM:T e C NUCLEAR (CORE CRITICAU
@ LIMIT 5 Y 400 - n 5 Psio 1260F CURVES A,8,C ARE VAUO 200 - r soLTu, FOR 22 EFPY OF OPERATION l
35'F MINIMUM CRIT 1CAUTY pr / TEMPERATURE = 96*F
/
0 b/
0 100 200 300 400 500 600
- MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F) l l
l OYSTER CREEK 3.3-9a Amendment NO. 151 l
l I
FIGURE 3.3 2 l OYSTER CREEK P-T CURVES VALID TO 27 EFPY 1600 A
re tarr 8 C 1400 I 3 1200 ) l I ,
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$ 800 f WITH ART OF 152'F FOR LOWER SHELL y PLATE G 8-6 w
2 A . SYSTEM HYOROTEST Llwi
[ WITH FUEL IN VESSEL E 600 B NON NUCLEAR p EATUS
[ 560 psig CooLDOWN *. MIT E
e C NUCLEAR (CCRE CRITICAL)
$ UMIT 5 )
400 - 27s PSio 0
126 F 200 - ; CURVES A.B.C ARE VALID soLTur r sS*F FOR 27 EFPY OF OPERATION MINIMUM CNTICAUTY j/
^
p TEMPERATURE = 96*F
/
O O 100 200 300 400 500 600 MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F) i l
3.3-9b OYSTER CREEK Amendment No. W
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1 FIGURE 3.3,3 OYSTER CREEK P-T CURVES VALID TO 32 EFPY
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l 1600 A
n am B C 1400 j t 3 1200 / i ! ,
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o 1 i b
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P-1000 w
w '
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FOR LOWER SHELL
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g J A SYSTEM HYOROTEST L'MIT g / _
W1TH FUEL IN ' ESSE.
D /
3 600 / B NON NUCLEAR HE ATUP.
" g CocLoewN uv:T -
w 560 psig i E
7 C NUCLEAR (CCRE CRITICAU g uMit -
w E
j[
- / CURVES A.B,C ARE VAUD
" "5 N ~
o FOR 32 EFPY OF OPERATION 126 F t%
APP G REQUIREMhMT BASED -
ON CURVE A 91100 PSIG 200 - saTuP r -
85*F
[/f d
_ _ _ MIMMUM CRITICAUTY TEMPERATURE = 96*F O t t t, f 0 100 200 300 400 500 600 MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F) 3.3-9c OYSTER CREEK Amendment No. 151
~
4.3 REACTOR COOLANT Applicability: Applies to the surveillance requirements for the reactor coolant system.
Objective: To determine the condition of the reactor coolant system and the operation of the safety devices related to it.
Specification: A. Materials surveillance specimens and neutron flux monitors shall be installed in the reactor vessel adjacent to the wall at the midplane of the active core. Specimens and monitors shall be periodically removed, tested, and evaluated to determine the effects of neutron fluence on the fracture toughness of the vessel shell materials. The results of these evaluations shall be used to assess the adequacy of the P-T curves A, B and C in Figures 3.3.1,3.3.2 and 3.3.3. New curves shall be generated l as required.
B. Inservice inspection of ASME Code Class 1, Class 2 and Class 3 I systems and components shall be performed in accordance with :
Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR, Section 50.55a(g), except where specific written relief has been granted by the NRC pursuant to 10 CFR, Section 50.55a(g)(6)(i).
C. Inservice testing cf ASME Code Class 1, Class 2 and Class 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR, Section 50.55a(g), except where specific written relief has been granted by the NRC pursuant to 10 CFR, Section 50.55a(g)(6)(i).
D. A visual examination for leaks shall be made with the reactor coolant l system at pressure during each scheduled refueling outage or aller i major repairs have been made to the reactor coolant system in accordance with Article 5000,Section XI. The requirements of specification 3.3.A shall be met during the test. ;
i E. Each replacement safety valve or valve that has been repaired shall be I tested in accordance with subsection IWV-3510 of Section XI of the ASME Boiler and Pressure Vessel Code. Setpoints shall be as follows:
Number of Valves Set Points (psig) 4 1212i12 5 1221 12 F. A sample of reactor coolant shall be analyzed at least every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for the purpose of determining the content of chloride ion and to check the conductivity.
OYSTER CREEK 4.3-1 Amendment No.: 82,90,120,150,151,164 l
l