PLA-5933, Proposed Amendment No. 280 to Unit 1, and Proposed Amendment No. 249 to Unit 2, Revise Technical Specification 3.4.10, RCS Pressure and Temperature (P/T) Limits

Proposed Amendment No. 280 to Unit 1, and Proposed Amendment No. 249 to Unit 2, Revise Technical Specification 3.4.10, RCS Pressure and Temperature (P/T) Limits

ML052850302
Person / Time
Site:	Susquehanna
Issue date:	10/05/2005
From:	Mckinney B Susquehanna
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-5933
Download: ML052850302 (53)

Text

Britt T. McKlnney Sr. Vice President & Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3149 Fax 570.542.1504 btmckinney@pplweb.com

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&A adl 0 i zou5 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop OP1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION PROPOSED AMENDMENT NO. 280 TO UNIT 1 FACILITY OPERATING LICENSE NPF-14 AND PROPOSED AMENDMENT NO. 249 TO UNIT 2 FACILITY OPERATING LICENSE NPF-22: REVISE TECHNICAL SPECIFICATION 3.4.10 "RCS PRESSURE AND TEMPERATURE (P/T) LIMITS" PLA-5933 Docket Nos. 50-387 and 50-388 In accordance with the provisions of 10 CFR 50.90, PPL Susquehanna, LLC is submitting a request for amendment to the Technical Specification 3.4.10 "RCS Pressure and Temperature (PIT) Limits" for Susquehanna SES Unit 1 and Unit 2.

The enclosure to this letter contains PPL's evaluation of these proposed changes.

Included are a description of the proposed change, technical analysis of the change, regulatory analysis of the change (No Significant Hazards Consideration and the Applicable Regulatory Requirements), and the environmental considerations associated with the change. to this letter contains the applicable pages of the Susquehanna SES Unit 1 and Unit 2 Technical Specifications (TS), marked to show the proposed changes. contains changes to the Technical Specification Bases (TSB) required as a result of the proposed TS changes. provides the detailed technical analysis used to develop the revised P/T limits curves for Susquehanna SES Units 1 and 2.

There are no regulatory commitments associated with these proposed Amendments which have been reviewed by the Susquehanna SES Plant Operations Review Committee and the Susquehanna Review Committee. PPL requests the NRC complete its review of the proposed changes by March 31, 2006, with the changes becoming effective within 30-days of NRC approval.

J*\\ I D Document Control Desk PLA-5933 Any questions regarding this request should be directed to Mr. Duane L. Filchner at (610) 774-7819.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on:

/c) s B. T. McKinney

Enclosure:

PPL Susquehanna Evaluation of the Proposed Changes Attachments: - Proposed Technical Specification Changes (Mark-ups) - Proposed Technical Specification Bases Changes (Mark-ups) - Structural Integrity Associates, Inc. Revised P/T Curves for SSES cc:

NRC Region I Mr. B. A. Bickett, NRC Sr. Resident Inspector Mr. R. V. Guzman, NRC Project Manager Mr. R. Janati, DEP/BRP

ENCLOSURE TO PLA-5933 PPL SUSQUEHANNA EVALUATION OF PROPOSED CHANGE UNIT 1 AND UNIT 2 CHANGES TO TECHNICAL SPECIFICATION 3.4.10

1.

DESCRIPTION

2.

PROPOSED CHANGE

2.

BACKGROUND

4.

TECHNICAL ANALYSIS

5.

REGULATORY ANALYSIS 5.1 No Significant Hazards Consideration 5.2 Applicable Regulatory Requirements/Criteria

5.

ENVIRONMENTAL CONSIDERATIONS

7.

REFERENCES

Enclosure to PLA 5933 Page 1 of 8 PPL EVALUATION

Subject:

UNIT 1 AND UNIT 2 CHANGE TO TECHNICAL SPECIFICATION 3.4.10

1.0 DESCRIPTION

In accordance with 10 CFR 50.90, this is a request to amend Facility Operating License Nos. NPF-14 and NPF-22 for PPL Susquehanna, LLC (PPL),

Susquehanna Steam Electric Station (SSES) Unit 1 and Unit 2. The proposed changes are to the SSES Technical Specification (TS) 3.4.10 "RCS Pressure and Temperature (PIT) Limits," which are revisions to the P/T Limits curves. The primary effect of the revision is to establish new limits on use of the P/T curves to 35.7 Effective Full Power Years (EFPY) for SSES Unit 1 and 30.2 EFPY for SSES Unit 2.

The calculations for the revised curves include a previously implemented power level increase from 3293 MWT to 3441 MWT, a feedwater instrument upgrade that increased power level from 3441 MWT to 3489 MWT, and a future power level uprate from 3441 MWT to 3952 MWT. The future increase is due to implementation of extended power uprate (EPU), for both SSES Unit 1 and SSES Unit 2, (See Attachment 3).

The revised PIT Limits curves were developed in accordance with 10 CFR 50 Appendix G, the 1998 Edition (2000 Addenda) of ASME Code,Section XI, Appendix G and are based in part on fluence calculations performed using the NRC approved BWRVIP RAMA Code methodology, (Reference 7.1). The RAMA Code methodology meets the intent of Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence."

The existing P/T Limits curves, in TS 3.4.10, were approved in Amendment Nos. 200 and 197 of Facility Operating License Nos. NPF-14 and NPF-22 for PPL SSES, Units 1 and 2, for use until May 1, 2006. Therefore, PPL requests approval of these proposed changes no later than March 31, 2006.

Enclosure to PLA 5933 Page 2 of 8

2.0 PROPOSED CHANGE

S The proposed changes are to TS Figures 3.4.10-1, 3.4.10-2, and 3.4.10-3, which show the P/T limits curves for inservice leakage and hydrostatic testing, non-nuclear heatup and cooldown, and criticality, respectively.

The proposed P/T limit curves are valid for 35.7 EFPY for SSES Unit 1 and 30.2 EFPY for SSES Unit 2. The plotted values of the proposed curves have been developed to be identical to the plotted values on the present curves, contained in NRC approved Amendments 200 and 197 for Unit 1 and Unit 2 respectively. Only the limit on the validity of the curves has changed. This change in validity is due to using new BWRVIP RAMA Code (Reference 1) fluence calculation methodology recently approved by the NRC. The new fluence calculations also incorporate the proposed EPU power level of 3952 MWT.

The EPU fuel core configuration used for the fluence calculation is a proposed design that assures extended power rating for a full 24 months. The fuel vendor created this design to show that it is possible to run at EPU power for a full cycle.

This proposed fuel load design provided for very conservative results for the fluence calculation method. The dates for the application of EPU used for the fluence calculation are starting in 2007 for Unit 2 and 2008 for Unit 1. These are the anticipated dates for initiation of EPU.

The marked-up TS pages are provided in Attachment 1 to this submittal. contains marked-up TS Bases pages as a result of the TS changes.

3.0 BACKGROUND

On July 17,2001, PPL submitted a license amendment request to update the P/T limit curves for SSES Unit 1 and SSES Unit 2 (Reference 7.2). The validity of the curves was established through May 1, 2006 for Unit 1 and May 1, 2005 for Unit 2. These curves were approved for use on February 7, 2002 as amendments 200 and 174 for SSES Unit 1 and SSES Unit 2 (Reference 7.3).

The validity date of the Unit 2 P/T limit curves was subsequently changed to May 1, 2006 by approved Unit 2 Amendment 197, dated April 25, 2005 (Reference 7.4).

The basis for NRC approval of the above license amendment requests was the conservatism in the estimated vessel irradiation at the end of life and at the end of the curve's valid period on May 1, 2006.

Enclosure to PLA 5933 Page 3 of 8 Since the existing Unit 1 and Unit 2 P/T Limit curves will be no longer valid after May 1, 2006, it is necessary to recalculate the curves and establish their validity.

The curves have been recalculated using the RAMA code for evaluation of the neutron flux through the core, vessel internals, and vessel geometry. Use of the RAMA code is acceptable based on NRC approval on May 13, 2005.

(Reference 7.1) 3.0 TECHNICAL SAFETY ANALYSIS OF THE PROPOSED CHANGES The P/T limits curves are prescribed during normal operation to avoid encountering pressure, temperature, and temperature rate-of-change conditions that might cause undetected flaws to propagate and cause nonductile failure of the reactor coolant pressure boundary, a condition that is unanalyzed. The operating limits for pressure and temperature are required for three categories of operation:

(a) hydrostatic pressure tests and leak tests, referred to as Curve A; (b) non-nuclear heatup/cooldown and low-level physics tests, referred to as Curve B; (c) core critical operations, referred to as Curve C.

The methodology used to develop P/T curves is described in Attachment 2. There are three regions of the RPV that are evaluated: (1) the beltline region, (2) the bottom head region, and (3) the feedwater nozzle/upper vessel region. These regions bound all other regions with respect to brittle fracture. The method of generating the curves is primarily the same for each region for both Curves A and B. The exception is the method used to create the upper vessel/feedwater region Curve B.

All components in the Reactor Coolant System (RCS) are designed to withstand the effects of cyclic loads due to system temperature and pressure changes.

Normal load transients, reactor trips, and startup and shutdown operations introduce these cyclic loads. During startup and shutdown, the rates of temperature and pressure changes are limited so that the maximum specified heatup and cool down rate are consistent with the design assumptions and satisfy the stress limits for cyclic operation.

The heatup and cooldown process for SSES Unit 1 and SSES Unit 2 is controlled by P/T limit curves, which are developed based on fracture mechanics analysis.

These limits are developed according to Appendix G of the ASME Boiler and Pressure Vessel Code,Section XI, and incorporate a number of safety margins.

Enclosure to PLA 5933 Page 4 of 8 The present SSES Unit I and SSES Unit 2 Technical Specification Figures 3.4.10 -1, 3.4.10-2, and 3.4.10-3 represent the reactor pressure vs.

minimum vessel temperature limits. The three curves (A, B, and C) are based on 10 CFR 50 Appendix G requirements of the ASME Boiler and Pressure Vessel Code,Section XI, and incorporate a number of safety margins.

As stated in the Background Section above, the applicability of the present curves is limited to May 1, 2006. This date was established due to the calculation methodology used to determine neutron fluence. The proposed change to the P/T curves establishes the applicability of the Unit 2 curves at 30.2 EFPY, and the applicability of the Unit 1 curves at 35.7 EFPY. It is estimated that on 5/1/2006 the actual exposure will be 19.01 EFPY for Unit 1 and 18.68 EFPY for Unit 2.

New fluence calculations were performed for the proposed curves utilizing the RAMA Code, and the impacts of EPU from 3489 MWT to 3952 MWT have been included. The plotted values of the proposed curves were developed to be identical to the plotted values of the currently approved curves in order to avoid changing the associated administrative procedures and to reduce the potential for human error. The effect of maintaining the curves identical is that the EFPY restriction on use has been recalculated to be 35.7 EFPY for Unit 1 and 30.2 EFPY for Unit 2.

5.0 REGULATORY SA`ETY ANALYSIS 5.1 No Significant Hazards Consideration The Commission has provided standards in 10 CFR 50.92(c) for determining whether a significant hazards consideration exists. A proposed amendment to an operating license for a facility 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; (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.

PPL proposes changes to Appendix A, Technical Specifications (TS), of Facility Operating License Nos. NPF-14 and NPF-22 for the Susquehanna Steam Electric Station (SSES) Units 1 and 2 respectively.

The proposed changes revise TS Section 3.4.10, "RCS Pressure and Temperature (P/T) Limits," by removing the valid date and replacing it with the Effective Full

Enclosure to PLA 5933 Page 5 of 8 Power Years (EFPY) of radiation exposure limit on each of the P/T curves for SSES Units 1 and 2.

In accordance with the criteria set forth in 10 CFR 50.92, PPL has evaluated the proposed TS change and determined it does not represent a significant hazards consideration. The following is provided in support of this conclusion.

1.

Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

No. The proposed changes request that the P/T limits curves in TS 3.4.10, "RCS Pressure and Temperature (P/T) Limits" be revised by removing the valid date and replacing it with the Effective Full Power Years of radiation exposure limit on each of the P/T curves for SSES Units 1 and 2.

The P/T limits are prescribed during all operational conditions to avoid encountering pressure, temperature, and temperature rate of change conditions that might cause undetected flaws to propagate, resulting in nonductile failure of the reactor coolant pressure boundary, an unanalyzed condition. Therefore, the proposed changes do not have any effect on the probability of an accident previously evaluated.

The P/T curves are used as operational limits during heatup or cooldown maneuvering, when pressure and temperature indications are monitored and compared to the applicable curve to determine that operation is within the allowable region. The P/T curves provide assurance that station operation is consistent with previously evaluated accidents. Thus, the radiological consequences of an accident previously evaluated are not increased.

Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

2.

Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

No. The proposed changes do not change the response of any plant equipment to transient conditions. The proposed changes do not introduce any new equipment, modes of system operation, or failure mechanisms.

Therefore, there are no new types of failures or new or different kinds of accidents or transients that could be created by these changes. The

Enclosure to PLA 5933 Page 6 of 8 proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.

3.

Does the proposed change involve a significant reduction in a margin of safety?

No. The consequences of a previously evaluated accident are not increased by these proposed changes, since the Loss of Coolant Accident analyzed in the FSAR assumes a complete break of the reactor coolant pressure boundary. The changes to the P/T limits curves do not change this assumption.

Therefore, the proposed changes do not involve a significant reduction in a margin of safety.

==

Conclusion:==

Based upon the above responses, PPL concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), "Issuance of Amendment," and, accordingly, a finding of no significant hazards consideration is justified.

5.2 Applicable Regulatorv Requirements/Criteria The P/T limits are not derived from Design Basis Accident (DBA) analyses. They are prescribed during normal operation to avoid encountering pressure, temperature, and temperature rate of change conditions that might cause undetected flaws to propagate and cause nonductile failure of the reactor coolant pressure boundary, a condition that is unanalyzed. Therefore, the P/T limits curves must be included in the Technical Specifications in accordance with 10 CFR 50.36(c)(2)(ii), "Limiting Conditions for Operation."

The proposed P/T curves, and the methodology used to develop them, comply with the requirements for monitoring fracture toughness, minimum temperature, and performing material surveillances in accordance with 10 CER 50 Appendix G, "Fracture Toughness Requirements, and the 1998 Edition (2000 Addenda) of ASME Code,Section XI, Appendix G."

Enclosure to PLA 5933 Page 7 of 8

6.0 ENVIRONMENTAL CONSIDERATION

10 CFR 51.22(c)(9) identifies certain licensing and regulatory actions, which are eligible for categorical exclusion from the requirement to perform an environmental assessment. A proposed amendment to an operating license for a facility does not require an environmental assessment if operation of the facility in accordance with the proposed amendment would not (1) involve a significant hazards consideration; (2) result in a significant change in the types or significant increase in the amounts of any effluents that may be released offsite; or (3) result in a significant increase in individual or cumulative occupational radiation exposure. PPL has evaluated the proposed change and has determined that the proposed change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Accordingly, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with issuance of the amendment. This deternination, using the above criteria, is:

0. As demonstrated in the No Significant Hazards Consideration Evaluation, the proposed amendment does not involve a significant hazards consideration.

0. There is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite. The proposed change does not involve any physical alteration of the plant (no new or different type of equipment will be permanently installed) or change in methods governing normal plant operation.

3. There is no significant increase in individual or cumulative occupational radiation exposure. The proposed change does not involve any physical alteration of the plant (no new or different type of equipment will be permanently installed) or change in methods governing normal plant operation.

6.0 REFERENCES

7.1 Letter from U.S. NRC to Bill Eaton (BWRVIP) Chairman Entergy Operations - Safety Evaluation of Proprietary EPRI Reports: "BWR Vessel and Internals Project, RAMA Fluence Methodology Manual (BWRVIP-114); RAMA Fluence Methodology Benchmark Manual Evaluation of Regulatory Guide 1.190 Benchmark Problems (BWRVIP-1 15); RAMA Fluence Methodology - Susquehanna Unit 2 Surveillance Capsule Fluence Evaluation for Cycles 1-5 (BWRVIP-1 17); RAMA Fluence Methodology Procedures Manual (BWRVIP-12 1); and Hope Creek Flux Wire Dosimeter

Enclosure to PLA 5933 Page 8 of 8 Activation Evaluation for Cycle 1 (TWE-PSE-001-R-001)

(TAC NO. MB9765)," dated May 13, 2005.

6.1 PLA-5341, letter from R. G. Byram (PPL) to U.S. NRC, "Proposed Amendment No. 240 to License NFP-14 and Proposed Amendment No. 205 to License NFP-22: Changes to Reactor Pressure Vessel Pressure-Temperature (P-T) Limits and Request for Exemption from the Requirements of IOCFR50 Section 50.50(a)," dated July 17, 2001.

6.1 Letter from U.S. NRC to R. G. Byram, "Susquehanna Steam Electric Station, Units 1 and 2 - Issuance of Amendment Re: Reactor Pressure Vessel Pressure-Temperature Limit Curves (TAC NOS. MB2516 and MB2518)," dated February 7, 2002.

6.1 Letter from U.S. NRC to B. L. Shriver, "Susquehanna Steam Electric Station, Unit 2 - Issuance of Amendment Regarding Reactor Pressure Vessel Pressure-Temperature Limits (TAC NO. MC4534)," dated April 25, 2005.

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RCS P/T Umits B 3.4.10 B 3.4 REACTOR COOLANT SYSTEM (RCS)

B 3.4.10 RCS Pressure and Temperature (PIT) Umits BASES BACKGROUND All components of the RCS are designed to withstand effects of cyclic loads due to system pressure and temperature changes. These loads are introduced by startup (heatup) and shutdown (cooldown) operations, power transients, and reactor trips. This LCO limits the pressure and temperature changes during RCS heatup and cooldown, within the design assumptions and the stress limits for cyclic operation.

This Specification contains PIT limit curves for heatup, cooldown, and 1.

inservice leakage and hydrostatic testing, and limits for the makimum rate of change of reactor coolant temperature. The heatup curve provides limits for both heatup and criticality.

Each PIT limit curve defines an acceptable region for normal operation. The usual use of the curves is operational guidance during heatup orcooldown maneuvering, when pressure and temperature indications are monitored and compared to the applicable curve to determine that operation is within the allowable region.

The 10O establishes operating limits that provide a margin to brittle failure of the reactor vessel and piping of the reactor coolant pressure boundary (RCPB). The vessel is the component most subject -to brittle failure.

Therefore, the LCO limits apply mainly to the vessel.

10 CFR 50, Appendix G (Ref. 1), requires the establishment of PIT limits for material fracture toughness requirements of the RCPB materials.

Reference 1 requires an adequate margin to brittle failure during normal operation, anticipated operational occurrences, and system hydrostatic tests.

It mandates the use of the ASME Code, Section Xl, Appendix G (Ref. 2).

The actual shift in the RTwT of the vessel material will be established periodically by removing and evaluating the irradiated reactor vessel material specimens, in accordance with ASTM E 185 (Ref. 3) and Appendix H of 10 CFR 50 (Ref. 4). The operating PIT limit curves will be adjusted, as necessary, based on the evaluation findings and the recommendations of Vesf=nel (Zaelul.

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,g X RCS P/T Umits B 3.4.10 The P/T limit curves are composite curves established by superimposing limits derived from stress analyses of those portions of the reactor vessel and head that are the most restrictive. At any specific pressure, temperature, and temperature rate of. change, one location within the reactor vessel will dictate the most restrictive limit. Across the span of the P/T limit curves, different locations are more restrictive, and, thus, the curves are composites of the most restrictive regions.

The heatup curve used to develop the PIT limit curve composite represents a different set of restrictions than the cooldown curve used to develop the P/T limit curve composite because the directions of the thermal gradients.

through the vessel wall are reversed. The thermal gradient reversal alters the location of the tensile stress between the outer and inner walls.

The criticality limits include the Reference I requirement that they be at least 40OF above the heatup curve or the cooldown curve and not lower than the minimum permissible temperature for the inservice leakage and hydrostatic testing.

The consequence of violating the LCO limits is that the RCS has been operated under conditions that can result in brittle failure of the RCPB, possibly leading to a nonisolable leak or loss of coolant accident In the event these limits are exceeded, an evaluation must be performed to determine the effect on the structural integrity of the RCPB components.

ASME Code, Section Xl, Appendix E (Ref. 6), provides a recommended.

methodology for evaluating an operating event that causes an excursion outside the limits.

q4 The P/T limits are not derived from Design Basis Accident (DBA) analyses.

They are prescribed during normal operation to avoid encountering pressure, temperature, and temperature rate of change conditions that might cause undetected flaws to propagate and cause nonductile failure of the RCPB, a condition that is unanalyzed. Reference 7 establishes the methodology for determining the P/T limits. Since the P/T limits are not derived from any DBA, there are no acceptance limits related to the P/T limits. Rather, the PIT limits are acceptance limits themselves since they preclude operation in an unanalyzed condition.

RCS P/T limits satisfy Criterion 2 of the NRC Policy Statement (Ref. 8).

I (continued)

SUSQUEHANNA - UNIT 1 TS I B 3.4-50 Revision 1

RCS P/T Limits B 3.4.10 BASES SREQUILEMENES SR 3A.10.7. SR 3.4.10.8. and SR 3.4.10.9 (continued)

The flange temperatures must be verified to be above the limits 30 minutes before and while tensioning the vessel head bolting studs to ensure that once the head is tensioned the limits are satisfied. When in MODE 4 with RCS temperature < 800F, 30 minute checks of the flange temperatures are required because of the reduced margin to the limits. When in MODE 4 with RCS temperature s 1000F, monitoring of the flange temperatire is required every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to ensure the temperature is within the specified limits.

The 30 minute Frequency reflects the urgency of maintaining the temperatures within limits, and also limits the time that the temperature liniits could be exceeded. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is reasonable based on the rate of temperature change possible at these temperatures.

REFERENCES

1. 10 CFR 50, Appendix G.

2. ASME, Boiler and Pressure Vessel Code, Section Xl, Appendix G.

3. ASTM E 185-73

4. 10 CFR 50, Appendix H.

5. Regulatory Guide 1.99, Revision 2, May 1988.

6. ASME, Boiler and Pressure Vessel Code, Section Xl, Appendix E.

7. NEDO-21778-A, December 1978.

8. Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132).

9. PPL Calculation EC-062-0573, "Study to Support the Bases Section of Technical Specification 3.4.10."

10. FSAR, Section 15.4.4.

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RCS PIT Limits B 3.4.1Q B 3.4 REACTOR COOLANT SYSTEM (RCS)

B 3.4.10 RCS Pressure and Temperature (PIT) Limits BASES BACKGROUND AJI components of the RCS are designed to withstand effects of cyclic loads due to system pressure and temperature changes. These loads are introduced by startup (heatup) and shutdown (cooldown) operations, power transients, and reactor trips. This LCO limits the pressure and temperature changes during RCS heatup and cooldown, within the design assumptions and the stress limits for cyclic operation.

This Specification contains PIT limit curves for heatup, cooldown, and inservice leakage and hydrostatic testing, and limits for the maximum rate of change of reactor coolant temperature. The heatup curve provides limits for both heatup and criticality.

Each PIT limit curve defines an acceptable region for normal operation. The usual use of the curves is operational guidance during heatup or cooldown maneuvering, when pressure and temperature indications are monitored and compared to the applicable curve to determine that operation Is within the allowable region.

The LCO establishes operating limits that provide a margin to brittle failure of the reactor vessel and piping of the reactor coolant pressure boundary (RCPB). The vessel is the component most subjectto brittle failure.

Therefore, the LCO limits apply mainly to the vessel.

10 CFR 50, Appendix G (Ref. 1), requires the establishment of PIT limits for material fracture toughness requirements of the RCPB materials.

Reference 1 requires an adequate margin to brittle failure during normal operation, anticipated operational occurrences, and system hydrostatic tests.

It mandates the use of the ASME Code, Section Xi, Appendix G (Ref. 2).

The actual shift in the RTwT of the vessel material will be established periodically by removing and evaluating the irradiated reactor vessel material specimens, in accordance with ASTM E 185 (Ref. 3) and Appendix H of 10 CFR 50 (Ref. 4). The operating PIT limit curves will be adjusted, as necessary, based on the evaluation findings and the recommendations of SUSQUIAN

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(fS^.t eJX I VI hlt 443 3t'Vffff 1Jt4io tALenre."(4111confinued)

Se sD 5 Tcc.oCn 4,1.5A t S-igfrt6r f1vs (ac d L)

SUSQUEHANNA - UNIT 2 TS / B 3.4-49 Revision 2

'C BASES Q A BACKG (contir 4-

,sf ri iwJ 3e 4-

-$ @EAPPLICD tatY SAETY ANALYS i

.J

)

3 3

j RCS P/T ULmits B 3.4.10 ROUND oed)

The P/T limit curves are composite curves established by superimposing limis derived from stress analyses of those portions of the reactor vessel and head that are the most restrictive. At any specific pressure, temperature, and temperature rate of change, one location within the reactor vessel will dictate the most restrictive limit Across tie span of the PIT limit curves, different locations are more restrictive, and, thus, the curves are composites of the most restrictive regions.

The heatup curve used to develop the PIT limit curve composite represents a different set of restrictions than the cooldown curve used to develop the PIT limit curve composite because the directions of the thermal gradients through the vessel wall are reversed. The thermal gradient reversal alters the location of the tensile stress between the outer and inner walls.

The criticality limits include the Reference I requirement that they be at least 40OF above the heatup curve or the cooldown curve and not lower than the minimum permissible temperature for the inservice leakage and hydrostatic testing.

The consequence of violating the LCO limits is that the RCS has been operated under conditions that can result in brittle failure of the RCPB, possibly leading to a nonisolable leak or loss of coolant accident In the event these limits are exceeded, an evaluation must be performed to determine the effect on the structural integrity of the RCPB components.

ASME Code, Section Xl, Appendix E (Ref. 6), provides a recommended methodology for evaluating an operating event that causes an excursion outside the limits.

\\BLE

ES The PIT limits are not derived from Design Basis Accident (DBA) analyses.

They are prescribed during normal operation to avoid encountering pressure, temperature, and temperature rate of change conditions that might cause undetected flaws to propagate and cause nonductile failure of the RCPB, a condition that is unanalyzed. Reference 7 establishes the methodology for determining the PIT limits. Since the P/T limits are not derived from any DBA, there are no acceptance limits related to the PIT limits. Rather, the PIT limits are acceptance limits themselves since they preclude operation in an unanalyzed condition.

RCS PIT limits satisfy Criterion 2 of the NRC Policy Statemnent (Ref. 8).

I (continued)

SUSQUEHANNA - UNIT 2 TS I B 3.4-50 Revision 1

RCS PIT Umits B 3.4.10 BASES (continued)

REFERENCES

1. 10 CFR 50, Appendix G.

2. ASME, Boiler and Pressure Vessel Code, Section Xt, Appendix G.

3. ASTM E 185-73

4. 10 CFR 50, Appendx H.

5. Regulatory Guide 1.99, Revision 2, May 1988.

6. ASME, Boiler and Pressure Vessel Code, Section Xl, Appendix E.

7. NEDO-21778-A, December 1978.

8. Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132).

9. PPL Calculation EC-062-0573, "Study to Support the Bases Section of Technical Speciflcation 3.4.10.I

10. FSAR, Section 15.4.4.

LA.

i SUSQUEHANNA - UNIT 2 TS / B 3.4-57 Revision 1 to PLA-5933 Structural Integrity Associates, Inc. Revised P/T Curves for SSES

Structural Integrity Associates, Inc.

68558 Havana Stret Suke 350 Certesm.,CO 80112-388 Phi:

303-792-0077 Faox 303-792-2158 June 8, 2005 GLS-05-016 SIR-00-167, Rev. I Mr. Bruce Swoyer PPL Susquehanna, LLC Two North Ninth Street Allentown,PA 18101-1179

Subject:

Revised Pressure-Temperature Curves for SSES

Reference:

PPL Purchase Order No. 305567-C dated 3/28/2005.

Dear Bruce:

The attachment to this letter documents the revised set of pressure-temperature (P-T) curves developed for Susquehanna Steam Electric Station Units I and 2 (SSES-I and SSES-2), in accordance with Structural Integrity's Quality Assurance Program. This work was performed in accordance with the referenced contract, and includes a full set of updated P-T curves (i.e., pressure test, core not critical, and core critical conditions) for 35.7 EFPY for SSES-l and 30.2 EFPY for SSES-2. The curves were developed in accordance with US. IOCFR 50 Appendix G, and the 1998 Edition (2000 Addenda) of ASME Code, Section Xl, Appendix G.

The inputs, methodology, and results for this effort are summarized in the attachment. The detailed calculations for this work (PPL-21Q-301, Rev. I and PPL-21Q-302, Rev. 1) are also attached.

Please don't hesitate to call me if you have any questions.

Prepared By:

ok Reviewed By:

1/

t Gary Stevens, P. E.

H. L. Gustin, P. E.

Senior Associate Associate Approved By:

A i.

Gary L. Stevens, P. E.

Senior Associate Attachment cc:

PPL-21Q-106, -301, -302, 401, SSES-19Q-106 Ausn. TX Ctauoue. NC IL ftnbitomCT San Joew, CA SiOW S6p'na, MD Sjuie. FL Unkontown OH Whbiler, CA 512-5334191 704-74554 1134050 4047w42 301445100

• 54472m 3304994753 24U444210

ATTACHMENT REVISED P-T CURVES FOR SUSQUEHANNA UNITS 1 & 2 1.0 Introduction This attachment documents the revised set of pressure-temperature (P-T) curves developed for the Susquehanna Steam Electric Station Units 1 and 2 (SSES-1 and SSES-2), in accordance with Structural Integrity's Quality Assurance Program. This work includes a full set of updated P-T curves (i.e., pressure test, core not critical, and core critical conditions) for SSES-1 for 35.7 effective full power years (EFPY) and for 30.2 EFPY for SSES-21. The curves were developed using the methodology specified in 10CFR50 Appendix G [4], WRC-175 (5], and the 1998 Edition (2000 Addenda) of ASME Code,Section XI, Appendix G [3].

2.0 ARTNDT Values Adjusted reference temperature (ARTNwr) values were developed for the SSES-1 and SSES-2 reactor pressure vessel (RPV) materials in the Reference [6] calculation. The values for a power increase from 3,293 MWT to 3,441 MWT were used in the current analysis.

3.0 P-T Curve Methodology The P-T curve methodology is based on the requirements of References {3] through [5]. The supporting calculations for the curves are contained in References [1] and [2]. There are three regions of the RPV that-are evaluated: (1) the beitline region, (2) the bottom head region, and (3) the feedwater nozzle/upper vessel region. These regions bound all other regions with respect to brittle fracture. The method of generating the curves is primarily the same for each region for both Curves A and B. The exception is the method used to create the upper vessel/feedwater region Curve B. That method will be described separately.

The approach used for the Curve A beltline, bottom head, and upper vessel/feedwater nozzle regions, and the Curve B beltline and bottom head regions, includes the following steps:

a.

Assume a fluid temperature, T. The temperature at the assumed flaw tip, T114t (i.e., 1/4t into the vessel wall) is determined by adding a temperature drop term, ATI,4t, to T.

For the SSES evaluation, the temperature drop term was conservatively set to zero.

'The ARTNDT values used in the P-T curve development include a power increase from 3,293 MWT to 3,441 MWT, a feedwater instrument upgrade that increased power from 3,441 MWT to 3,489 MWT, and a future projected equilibrium power uprate increase to 3,952 MWT, as defined in Table 3-2 of References [7] and 18].

Attachment to SIR-00-167, Rev. 1 I

b.

Calculate the reference fracture toughness, Kk, based on T114t using the relationship from Appendix G [3], as follows:

Kk= 20.734 eIO (TaI4I'tfM)I + 33.2 where:

T114t

=

metal temperature at assumed flaw tip (OF)

ARTN

=

adjusted reference temperature for location under consideration and desired EFPY (OF)

K=

reference fracture toughness (ks inch)

c.

Calculate the thermal stress intensity factor, Kit from ASME Code,Section XI, Appendix G [3].

d.

Calculate the allowable pressure stress intensity factor, K1P, using the foll6wing relationship:

Ku = (Kk-Kh)/SF where:

K1,

=

allowable pressure stress intensity factor (ksNlinch)

SF

=

safety factor

=

1.5 for pressure test conditions (Curve A)

=

2.0 for heatup/cooldown conditions (Curves B and C)

e.

Compute the allowable pressure, P, from the allowable pressure stress intensity factor, Kip. For the bottom head region, a stress concentration factor of 3 is included to account for the bottom head penetrations, consistent with WRC-175 methodology [5] and other BWR P-T curve evaluations.

f.

Apply any adjustments for temperature and/or pressure, such as for instrument uncertainty and the static head for the weight of the water in the RPV, to T and P. respectively.

g.

Repeat steps (a) through (f) for other temperatures to generate a series of P-T points.

The approach used for the Curve B upper vessel/feedwater nozzle region includes the following steps:

a.

Assume a pressure, P.

b.

Calculate the thermal stress intensity factor, Kit, by combining the secondary membrane stress intensity factor, Kin and the secondary bending stress intensity factor, Kp,, per IG-2222 of Appendix G [3] and including the correction factor, R, from Reference [5]:

Attachment to SIR 167, Rev. 1 2

Kit = R (Klm + Kmb) where:

R Kin Klb

=

correction factor, calculated to consider the nonlinear.

effects in the plastic region based on the assumptions and recommendations of WRC Bulletin 175 [5].

=

secondary membrane stress intensity factor

=

Mm*Osm

=

secondary bending stress intensity factor

=

(2/3)Mm*Csb The stress reports for the SSES feedwater nozzles did not provide sufficient detail for secondary stresses in the nozzle forging area. Therefore, the secondary stresses used in calculating the secondary membrane and bending stress intensity factors are those obtained from "generic" General Electric(GE) boiling water reactor P-T curve calculations (used to develop previous SSES P-T curves).

c.

Calculate the allowable pressure stress intensity factor, KV, based on the assumed P using the following relationship:

KV1

=

F(a/r,) (ap

+ Rapb)Yn/(a)

I, where:

F(a/r.)

Upm R

aypb a

=

nozzle stress factor, from Figure A5-1 of [5]

=

primary membrane stress

=

correction factor, defined above

=

primary bending stress

=

1/4t crack depth for nozzle corner (inches)

d.

Calculate the reference fracture toughness, Kic, using the following relationship:

Kk = K1, + K4,*SF where:

SF

=

safety factor = 2.0

e.

Compute the fluid temperature, T (assumed equal to the l/4t flaw temperature, TI/41), from the critical stress intensity factor Kic. The Kic equation from Appendix G [3] is manipulated to solve for TI/4t as follows:

T = 50

• In[ (Kic-33.2) / 20.734] + ARTNmr

f.

Apply any adjustments for temperature and/or pressure to T and P, such as for instrument uncertainty and the static head for the weight of the water in the RPV, respectively.

Attachment to SIR-00-167, Rev. 1 3

g.

Repeat steps (a) through (f) for other temperatures to generate a series of P-T points.

The following additional requirements were used to define the PrT curves. These limits are established in Reference [4]:

For Pressure Test Conditions (Curve A):

If the pressure is greater than 20% of the pre-service hydro test pressure (1,563 psig), the temperature must be greater than ARTNyrm of the limiting flange material + 900F.

If the pressure is less than or equal to 20% of the pre-service hydro test pressure, the minimum temperature is must be greater than or equal to the ARTNm of the limiting flange material + 600F. This limit has been a standard recommendation for the BWR industry for non-ductile failure protection.

For Core Not Critical Conditions (Curve B):

If the pressure is greater than 20% of the pre-service hydro test pressure, the temperature must be greater than RTNmr of the limiting flange material + 120 0F.

If the pressure is less than or equal to 20% of the pre-service hydro test pressure, the minimum temperature must be greater than or equal to the ARTNyr of the limiting flange material + 600F. This limit has been a standard recommendation for the BWR industry for non-ductile failure protection.

For Core Critical Conditions (Curve C):

Per the requirements of Table 1 of Reference [4], the core critical P-T limits must be 400F above any Pressure Test or Core Not Critical curve limits. Core Not Critical conditions are more limiting than Pressure Test conditions, so Core Critical conditions are equal to Core Not Critical conditions plus 400F.

Another requirement of Table 1 of Reference [4] (or actually an allowance for the BWR), concerns minimum temperature for initial criticality in a startup.

Given that water level is normal, BWRs are allowed initial criticality at the closure flange region temperature (ARTNmr + 600F) if the pressure is below 20% of the pre-service hydro test pressure.

Also per Table 1 of Reference [4], at pressures above 20% of the pre-service hydro test pressure, the Core Critical curve temperature must be at least that required for the pressure test (Pressure Test Curve at 1,100 psig). As a result of this requirement, the Core Critical curve must have a step at a pressure equal to 20% of the pre-service hydro pressure to the temperature required by the Pressure Test curve at 1,100 psig, or Curve B + 400F, whichever is greater.

The resulting pressure and temperature series constitutes the P-T curve. The P-T curve relates the minimum required fluid temperature to the reactor pressure.

4.0 P-T Curves Attachment to SER-00167, Rev. I 4

Tabulated values for the P-T curves are shown in Tables 1 through 14. The resulting P-T curves are shown in Figures 1 through 6.

Attachment to SER-OO-167, Rev. I 5

5.0 References

1. Structural Integrity Associates Calculation No. PPL21Q-301, Revision 1, "Development of Pressure Test (Curve A) P-T Curves," 06/08/05.

2. Structural Integrity Associates Calculation No. PPL-21Q-302, Revision 1, "Development of Heatup/Cooldown (Curves B & C) P-T Curves," 06/08/05.

3. ASME Boiler and Pressure Vessel Code, Section Xl, Rules for Inservice Inspection of Nuclear Power Plant Components, Nonmandatory Appendix G, "Fracture Toughness Criteria for Protection Against Failure," 1998 Edition including the 2000 Addenda.

4. U. S. Code of Federal Regulations, Title 10, Part 50, Appendix G, "Fracture Toughness Requirements," 1-1-04 Edition.

5. WRC Bulletin 175, "PVRC Recommendations on Toughness Requirements for Ferritic Materials," PVRC Ad Hoc Group on Toughness Requirements, Welding Research Council, August 1972.

6. Structural Integrity Associates Calculation No. SSES-19Q-301, Revision 0, "ARTNDT and ART Evaluation, 06/02/05.

7. PPL Nuclear Engineering Calculation No. EC-062-1107, Revision 0, "Final Report SSES Unit 1 RPV Fluence," TransWare Enterprises, Inc. Report No. PPL-FLU-002-R-002, Revision 0, "Susquehanna Unit 1 Reactor Pressure Vessel Fluence Evaluation," May 2005, SI File No. SSES-19Q-205.

8. PPL Nuclear Engineering Calculation No. EC-062-1105, Revision 0, "Final Report SSES Unit 2 RPV Fluence," TransWare Enterprises, Inc. Report No. PPL-FLU002-R-001, Revision 0, "Susquehanna Unit 2 Reactor Pressure Vessel Fluence Evaluation," May 2005, SI File No. SSES-19Q-204.

Attachment to SIR-O0-167, Rev. 1

,6

Table 1 Tabulated Values for SSES-1 Beltline Pressure Test Curve (Curve A) for 35.7 EFPY Inputs:

Plant =

Component =

Vessel thickness, t =

Vessel Radius, R =

ARTNDT =

K", =

ATIMI2 =

Safety Factor =

Mm=

Temperature Adjustment =

Pressure Adjustment =

Hydro Test Pressure =

Flange RTNDT =

SSES-1 Beltine 6.1875 126.6875 61.4 0.0 0.0 1.5 2.303 0.0 30 1,563 10.0 inches, so 4Jt-2.487 inches OF _->

35.7 EFPY ksiinchl" iAnch

'F (no thermal for pressure test)

{for pressure test)

I, psig (hydrostatic pressure for a full vessel) psig OF Fluid Temperature T

(F) 114t Temperature (en Kic Jksrlnch"2 )

70 75 80 85 90 95 100 105 110 115 120 70 75 80 85 90 95 100 105 110 115 120 57.83 60.42 63.28 66.44 69.94 73.80 78.07 82.79 88.00 93.77 100.14 Kip (ksl*inch 2) 38.55 40.28 42.18 44.29 46.62 49.20 52.05 55.19 58.67 62.51 66.76 Calculated Pressure P

(Pslg) 817 854 894 939 989 1043 1104 1170 1244 1325 1416 Adjusted Temperature for P-T Curve (7F) 70 70 75 80 85 90 95 100 105 110 115 120 Adjusted Pressure for P-T Curve (psig)

.0 787 824 864 909 959 1,013 1,074 1,140 1,214 1,295 1,386 Attachment to SIR-00-167, Rev. 1 7

Table 2 Tabulated Values for SSES-2 BeItline Pressure Test Curve (Curve A) for 30.2 EFPY Inowts:

Plant =

Component =

Vessel thickness, t =

Vessel Radius, R =

ARTNDT =

K,, =

ATIMIx =

Safety Factor =

Mm=

Temperature Aclustment =

Pressure Adjustment =

Hydro Test Pressure =

Flange RTT =

SSES-2 Beitline 6.1875 126.6875 46.7 0.0 0.0 1.5 2.303

. 0.0 30 1,583 10.0 inches, so 4!

inches.

OF ksi*inch" 2 2.487 finch 302 EFPY

°F (no thermal for pressure test)

(for pressure test)

OF psig (hydrostatic pressure for a full vessel) psig

°F Fluid Temperature T

(F) 1/4t Temperature (OF)

Calculated Pressure p

(PSlg)

Kic (ksl*inch 2)

Kip (kslinch"2) 70 75 80 85 90 95 100 105

• 70 75 80 85 90 95 100 105*

66.24 69.72 73.56 77.80 82.49 87.68 93.41 99.74 44.16 46.48 49.04 51.87 55.00 58.45 62.27 66.49 936 986 1040 1100 1166 1239 1320 1410 Adjusted Temperature for P-T Curve (7F) 70 70 75 80 85 90 95 100 105 Adjusted Pressure for P-T Curve (pslg) 0 906 956 1,010 1,070 1,136 1,209 1,290 1,380 Attachment to SLR4OO-167, Rev. 1 8

Table 3 Tabulated Values for SSES-I Feedwater Nozzle/Upper Vessel Region Pressure Test Curve (Curve A)

Inputs:

Plant =

Component =

ARTNDT =

Vessel thickness, t =

Vessel Radius, R =

F(a/m) =

Crack Depth, a =

Safety Factor =

Temperature Adjustment =

Pressure Adjustment =

Unit Pressure =

Flange RTNDT =

SSES-1 Upper Vessel 40.0 6.5 126.7 1.6 1.63 1.5 0.0 0.0 1,563 10.0 (based on FW nozzle)

'F All EFPY inches, so 4t 2.55 Ainch inches nozzle stress factor inches pF psig psig OF Fluid Temperature T

0 10 20 30 40 50 60 70 80 90 100 110 120 130 114t Temperature

(*F) 0 10 20 30 40 50 60 70 80 90 100 110 120 130 Kic (ksl*inch")

42.52 44.58 47.10 50.18 53.93 58.52 64.13 70.98 79.34 89.56 102.04 117.28 135.90 158.63 Calculated Pressure P

(oslap a

Kip (ksl~inch112) 28.34 29.72 31.40 33.45 35.96 39.02 42.75 47.32 52.90 59.71 68.03 78.19 90.60 105.76 402 421 445 474 509 553 606 670 750 846 964 1108 1284 1498 Adjusted Temperature for P-T Curve (70) 70 70 100 100 100 100 100 100 100

'100 100 100 100 100 110 120 130 Adjusted Pressure for P-T Curve (psig) 0 312.5 312.5 402 421 445 474 509 553 606 670 750 846 964 1108 1284 1498 Attachment to SIR00-16 7, Rev. I 9

Table 4 Tabulated Values for SSES-2 Feedwater Nozzle/Upper Vessel Region Pressure Test Curve (Curve A)

Inputs:

Plant =

SSES-2 Component =

Upper Vessel (based on FW nozzle) 0F===>

All EFPY ARTNDT =

Vessel thickness, t =

Vessel Radius, R =

F(a/m) =

Crack Depth, a =

Safety Factor =

Temperature Adjustment =

Pressure Adjustment =

Unit Pressure =

Flange RTNDT =

30.0 6.5 126.7 1.6 1.63 1.5 0.0 0.0 1,563 10.0 inches, so 4t inches 2.55 Anch.

nozzle stress factor inches pF psig psig OF I1 Fluid Temperature T

(OF) 0 10 20 30 40 50 60 70 80 90 100 110 120

! 114 Temperature Kic

('F)

(kslinchWm) 0 10 20 30 40 50 60 70 80 90 100 110 120 44.58 47.10 50.18 53.93 58.52 64.13 70.98 79.34 89.56 102.04 117.28 135.90 158.63 Kip (ksl*inchI 2) 29.72 31.40 33.45 35.96 39.02 42.75 47.32 52.90 59.71 68.03 78.19 90.60 105.76 Calculated Pressure P

(psig) 421 445 474 509 553 606 670 750 846 964 1108 1284 1498 Adjusted Temperature for P-T. Curve (IF) 70 70 100 100 100 100 100 100 100 100 100 100 100 100 110 120 Adjusted Pressure for P-T Curve (psig)

'0 312.5 312.5 421 445 474 509 553 606 670 750 846 964 1108 1284 1498 Attachment to SIR-00-167, Rev. 1 10

Table S Tabulated Values for SSES-1 Bottom Head Pressure Test Curve (Curve A)

In~uft Po

Compon, Vessel thicknes Vessel Radlu ART Safety Fact Stress Concentration Fac Temperature Adjustmi Heighli of Water for a Ful Vess Pressure Adjustnx Hydro Test Pressu Flange Rlrp lard =

SSES-1 erg = Bottom Head

s. t =

6.1875

, R=

126.6875 INMT=

34.0 Kg =

0.0 rl/=

0.0 tor=

1.5 tor =

3.0 WmI=

2.303 3rn =

0.0 el =

882.0 rit =

31.85 ure=

1,563 rwr=

10.0 inches, so 4t Inches ksi-inch'2 2.A7 AJinch All EFPY

°F (no thermal for pressure test)

(for pressure test)

Bottom head penetrations OF Inches psig Oydostafic pessixe at bottom head bra aA Usael at 706F) psig Fluid Temperature T

(T) 70 75 80 85 90 95 100 105 110 115 120 1/4t Temperature

(°F) 70 75 80 85 90 95 100 105 110 115 120 Kic (ksl*inchm2 )

75.80 80.28 85.23 90.70 96.75 103.43 110.82 118.98 128.00 137.97 148.99 Kip (ksl*inchr) 50.53 5352 56.82 60A7 64.50 6825 73.88 79.32 85.33 91.98 9933 Calculated Pressure p

J2~b) 714 757 803 855 912 975 1044 1121 1206 1300 1404 Adjusted Temperature for P-T Curve (OF) 70 70 75 80 85 90 95 100 105 110 115 120 Adjusted Pressure fr P-T Curve (Pat) 0 682 725 771 823 880 943 1,012 1,089 1,174 1,268 1,372 Attachment to SIR-00-167, Rev. I 11

Table 6 Tabulated Values for SSES-2 Bottom Head Pressure Test Curve (Curve A) inputs.

Plant =

Component =

Vessel thickness, t =

Vessel Radius, R =

ARTwT =

Kk =

,TIN =

Safety Factor =

Stress Concertration Factor =

Mm=

Temperature Adjustment =

Height of Water for a Full Vessel =

Pressure Adjustment =

Hydro Test Pressure =

Flange RTwT =

SSES-2 Bottom Head 6.1875 1266875 24.0 0.0 0.0 1.5 3.0 2.303 0.0 882.0 31.85 1,563 10.0 Inches, so 4t Inches

°F ksi*InchII 2.487 Ainch All EFPY IF (no thermal for pressure test)

(for pressure test)

Bottom head penetrations I.

Inches psig (hydrostatic pressure at bottom head for a kill eael at 70F) psig eF Fluid Temperature T

(F) 70 75 80 85 90 95 100

• 105 110 114t Temperature CFp) 70 75 80 85 90 95 100 105 110 Kic (kslinch"2) 85.23 90.70 96.75 103.43 110.82 118.98 128.00 137.97 148.99 Kip (ksrinchla )

56.82 60.47 64.50 68.95 73.88 79.32 85.33 91.98 99.33 Calculated Pressure p

(psig) 803 855 912 975 1044 1121 1206 1300 1404 Adjusted Temperature for P-T Curve (F) 70 70 75 80 85 90 95 100 105 110 Adjusted Pressure for P-T Curve (psig) 0 771 823 880 943 1,012 1,089 1,174 1268 1,372 Attachment to SIR 167, Rev. 1 12

Table 7 Tabulated Values for SSES-1 Beitline Core Not Critical Curve (Curve B) for 35.7 EFPY Inputs:

Plant =

Component =

Vessel thickness, t =

Vessel Radius, R =

ARTNM =

Cooldown Rate =

Kit=

Safety Factor =

Mm=

Temperature Adjustment =

Pressure Adjustment =

Flange RTwT =

SSES-1 Beltline 6.1875 inches, so 126.6875 inches 61.4 OF 100.0 eF/hr 9.08 ksl*inchll 2 2.0

-At 2.487 4inch 35.7 EFPY 2.303 0.0 30.0 10.0 Kip (ksrinch' 2) psig (hydrostatic pressure for a full vessel)

OF Fluid Temperature T

(F) 1/4t Temperature (F)

Calculated Pressure P

(psig)

Klc (ksl*lnch' 2) 70 75 80 85 90 95 100 105 110 115 120 125 130 135 140 145 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 145.0 57.83 60.42 63.28 66.44 69.94 73.80 78.07 82.79 88.00 93.77 100.14 107.18 114.96 123.56 133.06 143.56 24.37 25.67 27.10 28.68 30.43 32.36 34.50 36.86 39A6 42.35 45.53 49.05 52.94 57.24 61.99 67.24 517 544 575 608 645 686 731 782 837 898 965 1040 1123 1214 1314 1426 Adjusted Temperature for P-T Curve (eF) 70 70 75 80 85 90 95 100 105 110 115 120 125 130 135 140 145 Adjusted Pressure for P-T Curve (psig) 0 487 514 545 578 615 656 701 752 807 868 935 1010 1093 1184 1284 1396 Attachment to SIR-O167, Rev. 1 13

Table 8 Tabulated Values for SSES-2 BeItline Core Not Critical Curve (Curve B) for 30.2 EFPY Inputs:

Plant =

Component =

Vessel thickness, t =

Vessel Radius, R =

ARTNDT =

Cooldown Rate =

K%=

Safety Factor =

Mm =

Temperature Adjustment =

Pressure Adjustment =

Flange RTNDT =

SSES-2 Beltline 6.1875 126.6875 46.7 100.0 9.08 2.0 2.303 0.0 30.0 10.0 inches, so 4t inches

°F 2.487 Inch 30.2 EFPY

°F/hr ksi*inch" 2 pF

(

psig (hydrostatic pressure for a full vessel)

I.

Fluid Temperature T

(F) 1/4t Temperature (OF)

KIc (ksPinch"1 )

70 75 80 85 90 95 100 105 110 115 120 125 130 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 66.24 69.72 73.56 77.80 82.49 87.68 93.41 99.74 106.74 114.47 123.02 132.46 142.90 Kip (ksl*lnch"2) 28.58 30.32 32.24 34.36 36.71 39.30 42.17 45.33 48.83 52.70 56.97 61.69 66.91 Calculated Pressure P

(psig) 606 643 684 729 778 833 894 961 1035 1117 1208 1308 1419 Adjusted Temperature for P-T Curve (OF) 70 70 75 80 85 90 95 100 105 110 115 120 125 130 Adjusted Pressure for P-T Curve (ps1g) 0 576 613 654 699 748 803 864 931 1005 1087 1178 1278 1389 Attachment to S1R400-167, Rev. 1 14

Table 9 Tabulated Values for SSES-1 Upper Vessel/Feedwater Nozzle Region Core Not Critical Curve (Curve B)

POan

• GSES-1 Comiponent.- Upper Vessel ART,w, -

am.

os..

Safety Factor.

F(afrj -

Tenmperatsa A4uatrrent -

Presswe Adjustmet =

Hydro Teoo Pressure.

Range RTCT -

40.0 T

AN EFPY

20.

k O 1050 psig 022 hal 1050 psig 1.119 ki O 546 F 1S.4 kalO 546 F 45.0 hal 2.4 z.

18 0.0

• F 0L.

pat 1563 psig 10.0

• F Pase TeMP 0.F 00 F 1.

Pressure P

fpsQ 50 100 150 185.9 200 250 3SO 312.5 312.5 350 400 450 5W 550 600 614 650 750 800 850 WOO 950 1000 1050 1100 1150 1200 1250 1300 saturation Teeratuwre 297.3 237.7 3S5.8 373.4 367.9 40K.2 422.1 425.7 425.7 436.0 448.5 4599 470.4 480.1 489.1 491.6 497.

5057 5132 520.4 527.3 33.9 540.1 546.2 552.0 557.8 563.0 5682 573.3 578.2 a..

9Pb

a.

a 0.98 1.95 2.93 324 3.90 4.88 5.85 6.10 6.10 6.113 7.81 6.78 9.76 10.73 11.71 t11.

12.68 13.68 14.64 15.61 16.5S 17.56 18.54 19.51 204S 21.47 22.44 23.42 24.39 25.37 0.01 0.02 0.03 QC03 0.04 0.05 Q0.

0.07 0.0 0.07 o0e 0.0 0.10 0.12 0.13 0.13 0.14 0.15 0.16 0.17 0.18 0.19 020 0.21 022 023 024 025 026 027 7.36 8.65 8.79 10.34 9.79 11.52 10.06 1183 110.5 12A4 11.23 1320 11.79 13.86 11.92 14.02 11.92 14.02 12.28 14.45 12.73 14.97 13.13 15.4S 13.51 158M 13.85 16.2 14.17 16.7 1426 16.77 14.47 17.02 14.76 1735 15.03 17A7 1523 17.7 1S.3 18.26 15.76 18.53 1S.8 1E6.0 1620 19.0S 16.40 1029 16.60 19.52 16.79 19.75 16s9 19.97 17.16 20.18 17.3 20.38 Gew tksO) 17.00 21.11 2427 25.16 26.96 29.36 21.57 32.10 32..10 33.63 35.59 37.45 3925 40.99 42.67 43.13 44.31 45.92 47.49 4SM 50.55 52.04 53.52 54S7 56.40 57.82 5923 60.62 e1.99 63.36 A

1wo0 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.O 1.00 1.00 1.00 o0.7 0.93 10.8 O0.4 0.80 0.76 0.73 IM 0.69 OAS 0.86 0.63 0.59 0.56 0.53 Total Klt lap ac Ikslnchn) W chu) (klwnch" 23.3 32 41.0 39.6 7.7 55.1 44.3 11.5 67.3 455 12.7 71.0 47.9 15.3 78.

60.8 192 88.1 53.3 23.0 994 53.9 24.0 101.9 63.9 24.0 019 55.6 26.8 109.3 57.6 30.7 118.s 59.4 4.5 1284 61.1 28.3 137.8 62.7 42.2 147.0 64.1 46.0 156.1 64.5 47.1 15s.7 65.5 49.9 1652 64.9 53.7 172.3 63.0 57.5 178.0 61.1 61.3 183.6 59.1 85.1 189.3 572 68.9 195.0 55.3 72.7 200.6 53A 76.5 206.3 514 80.3 212.0 49.5 84.1 217A 47.6 87.6 223.3 45.6 91.6 228.9 43.7 95.4 234.6 41.6 99.2 2402 Calculsted Terrpemure 0.0 0.0 64.0 70.0 79.1 88.6 98.0 58.9 99.9 105.0 111.0 116.2 120.0 125.1 129.0 130.0 132.5 185.2 137.2 138.1 140.9 142.7 1444 146.1 147.7 149.3 150.8 152.2 1153.7 155.0 Adft AcQuatd Tomperaw,.

Pressure for br P-TCuv P-T Curve ff)

Ipsig 70.0 0

70.

100 70.0 150

70.

166 79.1 200 MI 250 O80 300 o99 312.5 130.0 812.5 120.0 350 120.0 400 1201 450 10.0 500 130.0 550 130.0 614 132.5 650 152 700 1372 7oo 139.1 S00 148.9 8450 12.7 OS 144A 950 1461 1000 147.7 1050 149.3 1100 150.

1150 1522 1200 15.7 1250 1550 1300 Attachment to SIR-00-167, Rev. 1 15

Table 10 Tabulated Values for SSES-2 Upper Vessel/Feedwater Nozzle Region Core Not Critical Curve (Curve B) t Plant a SSES-2 Compofet.

UpWe Vels\\

AMT1,w 3* 0.0

'F JI EFY ea,,.

20.48 bil C l1050ps4g OM.

022 klW low paig BaseTemp n

1t.19 kW e 546F 90 F

@eb 1L04 kilO 64IF 90'OF a'..

45.0 kal k4*

2.54 Sasety Fccbr*

2.0 Flef.h 1.8 Teriperahr A4usbnien 0.0 IF Preuure A4usbient 0.0 psig Hydro Text Presawe-IS63 p69 Flanue RrT-10.0 F

acubled AduLd Adjusled Pressure SUenation Tout Tetllprure Temperature Prssurs tor P

Temertue Op U b

0-06b GW X

Kit lap 10c T

orP.TCwe P-TCuve (P9al) m

()

Owl) fka)

&&Q

&80 R

ks ch'5 (kswhn (k*knwh5

() RF (Palo) 70.0 0

50 297.3 06 0.01 7.36 6es 17.00 1.00 33.3 3.8 41A 0.0 70.0 50 100 337.7 1.5 0.02 8.79 10.34 21.11 1.00 39.8 7.7 55.1 0.0 T0.

100 50 365.8 2.3 0.03 9.79 1152 2427 1.00 44.3 11.8 67.3 54.9 700 150 200 387.s 3St 0.04 1058 1244 26.96 1.0 47.9 15.3 7e.8 69.1 70D 200 203.7 3894 336 0.04 10.03 12.50 27.15 1.0 48.1 15.6 79.3 70.0 70.0 204 250 4062 4.88 O.5 1123 13.20 29.36 1.00 50.8 19.2 9.1 79.6 79 250 300 422.1

.5.85 0.06 11.79 136 31.57 1.00 53.3 23.0 994 88.0 I0 30 312.5 425.7 6.10 0.07 11.2 14.02 32.10 1.00 53.0 24.0 101.9 89.0 130.0 312.5 312.5 425.7 6.10 0.07 11.2 14.02 32.10 1.0 839 24.0 101.8 89.9 130.0 312.5 350 438o 6.83 07 1228 14,45 m3 1.00 55.6

.268 100.3 95.0 130.0 350 400 4483 7.81 008 12.73 147 35.5 1.00

67.

30.7 118.

101.0 130.0 400 450 4599 6.73 0.09 13 15A.5 37A5 1.00 80.4 34.5 128.4 1082 130.0 450 500 4704 9.76 0.10 13.51 158 39.25 1.00 61.1 38.3 137.0 110.9 10.o soo 55C 4I 10.73 0.32 13.5 1629 40.99 1.00 62.7 422 147.0 115.1 130.0 S50 o0 489.1 11.71 0.13 14.17 1e67 42.67 1.00 64.1 46.0 156.1 119.0 130.0 600 850 497j.

12.88 0.44 1447 17.02 44.31 1O0 65.5 49s 1652 122.5 130.0 C50 700 505.6 13.86 0.15 14.76 17.35 45.92 0t7

64.

53.7 172.3 1252 130.0 700 750 5132 14.64 0.16 15.03 17.67 47.9 033 83.0 57.5 178.0 127.2 13.0 750 757 514.

14.77 0.16 15.06 17.71 47.71 032 82.7 58.0 178.7 127A

13.

757 So 5204 15.61 0.17 1526 1737 49.03 O08 61.1 61.3 183.6 129.1 130.0 80 825 823.

16.10 0.17 15A1 18.12 40.79 0.86 80.1 632 186.5 130.0 13.0 825 850 5273 168 0.18 15.8 18.26 50.55 0.84 59.1 65.1 189.3 130.9 10 850 900 5332 17.6 0.19 15.76 18.3 52.04 0.80 572 8.8 195.0 132.7 132.7 oc 950 540.1 18.4 0.20 1538 18.80 53.52 0.76 55.3 72.7 200.6 1344 134A 050 10.0 5452 19.51 021 16.2 19.0 54s7 0.73 53.4 765 206.3 136.1 1361 1000 1050 552.0 20.49 0.22 1640 1929 56.40 0.69 51.4 0.3 212.0 137.7 137.7 1050 1100 557.6 21.47 023 16.0 19.2 57.82 0.86 495 84.1 217.

139.3 1i31 1100 1150 s3.0 22.44 024 16.79 19.75 59.23 0.83 47.6 87.3 223.3 4.8 140.8 1150 1200 5682 23.42 0.25 1636 1937 60.82 o5 45.6 S1.

2263 142.2 142.2 1200 1250 5R3 24.39 026 17.16 20.18 6139 0.56 43.7 95A 234.6 143.7 143.7 1250 1300 582 25.37 027 17.33 203 63.36 053 41.8 902 240.2 145.0 1450 1300 Attachment to SIR-00-167, Rev. 1 16

Table 11 Tabulated Values for SSES-1 Bottom Head Core Not Critical Curve (Curve B)

Inputs:

Plant =

Component =

Vessel thickness, t =

Vessel Radius, R =

Cooldown Rate =

Safety Factor =

Stress Concentration Factor =

ARTN,,T =

Mm=

Kft=

Temperature Adjustment =

Height of full vessel =

Pressure Adjustment =

Unit Pressure =

Flange RTNDT =

SSES-1 Bottom Head 6.1875 126.6875 100.0 2.0 3.0 34.0 2.303 9.08 0.00 882.0 31.85 1563 10.0 (Penetrations Portion) inches, so 4t 2.487 inches

'F/hr OF-

===>

All EFPY ksl*inchll 2 OF inches psig psig OF

'inch I.

Fluid Temperature T

1*F1 114t Temperature Kic Kip (ksl*lnchl 2)

(eF1 (ks*linch"2)

--- L-A 70 75 80 85 90 95 100 105 110 115 120 125 130 135 140 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 135.0 140.0 75.80 80.28 85.23 90.70 96.75 103.43 110.82 118.98 128.00 137.97 148.99 161.17 174.63 189.50 205.94 33.36 35.60 38.08 40.81 43.84 47.18 50.87 54.95 59.46 64.45 69.96 76.05 82.78 90.21 98.43 Calculated Pressure P

(psig) 472 503 538 577 620 667 719 777 841 911 989 1075 1170 1275 1391 Adjusted Temperature for P-T Curve (7F) 70 70 75 80 85 90 95 100 105 110 115 120 125 130 135 140 Adjusted Pressure for

• P-T Curve (Psig) 0 440 471 506 545 588 635 687 745 809 879 957 1043 1138 1243 1360 Attachment to SIR-00-167, Rev. I 17

Table 12 Tabulated Values for SSES-2 Bottom Head Core Not Critical Curve (Curve B)

Inputs:

Plant =

Component =

Vessel thickness, t =

Vessel Radius, R =

Cooldown Rate =

Safety Factor =

Stress Concentration Factor =

ARTNOT =

SSES-2 Bottom Head 6.1875 126.6875 100.0 2.0 3.0 24.0 (Penetrationr Portion) inches, so At 2.487 inches

'F/hr OF====->

All EFPY 4inch Mm =

2.303 1C, =

9.08 Temperature Adjustment =

0.00 Height of full vessel =

882.0 Pressure Adjustment =

31.85 Unit Pressure =

1563 Flange RTNDT =

10.0 ksi'inch12 OF inches psig psig eF Fluid Temperature T

(eF) 70 75 80 85 90 95 100 105 110 115 120 125 130 114t Temperature (F)

Kic (ksl-inchl" Klp (ksi*lnchl m)

Calculated Pressure P

(pslg) 70.0 75.0 80.0 85.0 90.0 95.0 100.0 105.0 110.0 115.0 120.0 125.0 130.0 85.23 90.70 96.75 103.43 110.82 118.98 128.00 137.97 148.99 161.17 174.63 189.50 205.94 38.08 40.81 43.84 47.18 50.87 54.95 59.46 64.45 69.96 76.05 82.78 90.21 98.43 538 577 620 667 719 777 841 911 989 1075 1170 1275 1391 Adjusted Temperature lor P-T Curve (eF) 70 70 75 80 85 90 95 100 105 110 115 120 125 130 Adjusted Pressure for P-T Curve (pslg) 0 506 545 588 635 687 745 809 879 957 1043 1138 1243 1360 Attachment to SIR-00-167, Rev. 1 18

Table 13 Tabulated Values for SSES-1 Core Critical Curve (Curve C) for 35.7 EMPY MM-Plant

• SSES-1 Component.

Upper Vessel ARTCT =

40.0 OF op.

• 20A9 kl C 1l50 psig

°,,

0.22 kslC 1050psig BaseTemp a,,,

16.19 ksl 8 46 IF 90 OF aet.

19.04 kWlO 648 F 90 g

F c, -

45.0 kWi M.,.

2.64 Safety Facor W

2.0 F(ar,,)

1.6 Temperture A4ustment-0.0 IF Pressure Adjustment 0.0 ps1g Hydro Test Pressure 1563 pig Flange RTMT 10.0 IF I.

Pressure Saturation Total P

Temperature 80 81.4 100 tOO 150 200 250 SOO 812.8 S12.5 S50 400 450 800 850 600 614 650 7Wo 750 8oo 850 900 950 1000 1050 1100 1180 1200 1250 1300 (rF) 297.3 S24.7 337.7 865.8 887.9 4062 422.1 425.7 425.7 436.0 448.5 459.9 470.4 480.1 489.1 491.6 497.6 506.6 513.2 820.4 827.8 633.9 840.1 64.2 852.0 857.6 883o 88.2 87S.8 8762 Ip=

@p cam 6m uw Klt Kip Kbc (ksl)

(kal)

(ksl) (ksl)

(ks$

R

srlnchWkwhchrkxrkbch-0.98 0.01 7.86 8.85 17.00 1.00 33.8 8.8 41.0 1.89 0.02 8.83 9.80 19.78 1.00 37.7 62 802 1.95 0.02 8.79 10.84 21.11 1.00 89.8 7.7 85.1

.93 0.03 9.79 11.52 2427 1.00

44.

11t.

67.

8.90 0.04 10.88 12.44 26.96 1.00 47.9 18.8 78.5 4.880 0 1123 18.20 29.8 1.00 60.8 192 89.1 6.5 0.06 11.79 1.86 81.87 1.00 88.3 23.0 99.4 6.10 O

11.92 14.02 82.10 1.00 88.9 24.0 101.9 6.10 0.07 11.92 14.02 82.10 1.00 88.9 24.0 101.9

.83 O0 12.28 14A.5 3.63 1.00 85.6 268.

109.8 7.1 0.08 12.73 14.97 85.89 1.00 67.6 80.7 118.9 8.78 Q09 t13t 15.45 87.45 1.00 89.4 34.8 128.4 9.76 Q010 18.1 18.88 3925 1.00 61.1 88.8 187.

10.73 0.12 18.85 1629 40.99 1.00 62.7 42.2 147.0 11.71 0.18 14.17 16.67 42.67 1.00 64.1 46.0 156.1 11.98 0.13 14.26 16.77 48.1S 1.00 64.5 47.1 158.7 12.68 0.14 14.47 17.02 44.81 1.00 e5.6 49.9 1652 18.66 0.15 14.76 175 45.92 0.97 64.9 837 172.8 14.64 0.16 18.08 17.67 47.4S 0.93 63.0 87.6 178.0 15.61 Q17 1828 17.97 49.03 0.88 61.1 61.8 183.6 16.9 0.18 15.S8 1826 80.65 0.84 89.1 65.1 189.8 17.86 0.19 18.76 18.88 62.04 0.80 672 88.9 195.0 1654 020 15.98 18.80 68.52 0.76 85.8 72.7 200.6 19.8 021 1620 19.05 54.97 0.73 63.4 76.8 206.8 20.4S 022 16.40 1929 56.40 0.69 81.4

80.

212.0 21.47 0.23 16.60 19.82 67.82 066 49.5 84.1 217.6 22.44 024 16.79 19.75 6923 0.63 47.6

87.

223.8 23.42 025 1698 19.97 60.62 0.8 45.6 91.6 228.9 24.89 026 17.16 20.18 61.99 0.8 43.7 95.4 284.6 25.87 027 17.8 20.8 63.86

0.

41.8 992 2402 Calculated Adjustd Adjusted Temperature Temperature Pressure for T

for P-T Cune P-T Curve (5F)

(Psal) 7 0.0 0

70.0 60 30.0 700 e1 42.8

a.

100 64.9 104.

150 79.1 l19.

200 89.6 129.6, 250 98.0 138.

SOO 99.9 1t 812.8 99.9 1nu.

812.8 105.0 1t 40 111.0 1N.

400 116.2 17C0 450 120.9 170.0 8CO 125.1 170.0 50 129.0 17.0 600 180.0 170.0 614 182.5 1725 650 185.2 1782 700 1S7.2 1772 780 139.1 179.1 So 140.9 1809 850 142.7 182.7 900 144.4 184.4 950 146.1 8661 1000 147.7 187.7 1050 149..

189.8 1100 150.8 190.

1180 152.2 192 1200 183.7 193.7 1250 155.0 195.0 1800 Attachment to SIR-00-167, Rev. 1 19

Table 14 Tabulated Values for SSES-2 Core Critical Curve (Curve C) for 30.2 EPPY Plant

• SSE-.2 Component-Upper Vessel ARTmT-30.0 IF a,.

20.49 kBi C 1050 psig apb 0.22 ksl C lS0 psig BaseTefnp c,

16.19 kh i C 46 IF 90 F a°b 19.04 Wk 546 IF 90 F 0 w.

45.0 Wsi U., -

2.54 Safety Fscbr 2.0 F(ar.

• 1.6 Tenmeruaure Adustrmet

• 0.0 F

Pressae Adjustment.

0.0 psig

'Hydro Test Presu e.

1t63 psd Flange RTmT

• 10.0

• F Pressure aturation P

T"Vare

1. wsb) mF) 80 2s7.3

95.

334.7 100 337.7 180 385.8 200 387.9 250 4062 300 422.1 312.5 425.7 312.5 425.7 350 436.0 400 448.5 450 459.

500 470.4 550 480.1 600 4B8.1 650 497.6 700 505.6 750 513.2 757 514.3 W00 520.4 825 523.0 850 527.3 9X0 533.9 950 840.1 1000 5462 1050 S52.0 1100 557.6 1150 563.0 1200 86E2 1250 573.3 1300 578.2 ap.

ab 6

Gb

&SOc (tksl

&s) 0)

098 0.01 7.36

.a8s 1.86 0.02 6.69 10.22 1.95 0.02 679 1034 2.3 0.03 9.79 11.52 3890 0.04 10.8 12.44 4.68 0.05 1123 1320 8.65 0.06 11.79 13*8 6.10 0.07 1192 14.02 6.10 0.07 11.92 14.02 6.3 0.07 1228 14.45 7J1 0.08 12.73 14.97 6.78 0o.9 13.13 15.4s 0.76 0.10 13.1 15.68 10.73 0.12 13.5 16.29 11.71 0.13 14.17 16.67 12.6 4.14 14.47 17.02 13.6 0.15 14.76 17.35 14.64 O.16 15.03 17.67 14.77 0.16 15.06 17.71 15.61 0.17 1528 17.7 16.10 0.17.

15.41 1L812 1659 0.16 15.83 18.26 175 0.19 15.76 18.53 16.54 0.20 15.88 18.80 19.51.

021 1620 19.05 20.4S 0.22 16.40 1929 21.47 0.23 16.60 19.82 22.44 0.24 16.79 19.75 23.42 0.25 168 19.97 24.39 026 17.16 20.18 25.37 027 17.33 20.38 ab" 17.00 20.71 21.11 2427 26.6 29.38 3157 32.10 32.10 3363 35.58 37.45 39.25 4099 42.67 44.31 45.92 4749 47.71 49.03 49.79 s0.55 52.04 53.52 5497 568.O 57.82 59.23 60.62 6199 63.38 KIt l0P R -

silnch'slst"tnch"N 1.00 33.3 3.8 1.00 39.3 7.3 1.0

39.

7.7 1.00 44.3 11.5 l.00 47.9 15.3 1.00 50.8 192 1.00 53.3 23.0 1.00 53.9 24.0 1.00 53.9 24.0 1.00 85.6 26.8 1.00 57.6 30.7 10 89A4 34.5 1.00 61.1 38.3 1.00 62.7 42.2 1.00 64.1 48.0 1.00 65.5 499 0W7 54.9

.53.7 0.93 63.0 57.5 0.92 62.7 58.0 0.68 61.1 61.3 0.66 60.1 63.2 0.84 59.1 6.1 0.60 572 68s 0.76 55.3 72.7 0.73 53.4 76.5 0.69 S1A 80.3 0.66 49.5 84.1 0.63 476 67.

O05 45.6 91.6 O.6 43.7 95.4 O03 41.8 99.2 Colculated "uded Adjustd Tows TemPersture Temperetwr Pressure for Kkc T

IorP.TCum P-T Curv,

70.

0 41.0 700 so 54.0 30.0 7M0 96 55.1 32.8 72 100 673

64.

I49 150 78.5 69.1 109.1 200 89.1 79.6

11.

250 9G.4 88.0 125.0 300 101.9 60.9 129.

312.5 101.0 6s9.

70 312.5 109.3 05.0 1m 350 e1.9 101.0 11U 400 128.4 106.2 W3.

450 137.

110.9 1.0 S00 147.0 115.1 MAon 550 156.1 11.0 170.0 600 165.2 122.5 170.0 50 172.3 125.2 170.0 700 178.0 127.2 170.

750 178.7 127A 170.

757 183.6 129.1 170.0 a00 186.5 130.0 170.0 825 189.3 130.9 170 850 1950 132.7 172.7 900 200.

134A4 174.4 950 206.3 136.1 176.1 1000 212.0 137.7 7.7 1050 217.6 13932 179.3 1100 2233 140.6 160.6 1150 228.0 142.2 162.2 1200 234.6 143.7 163.7 1250 2402 145.0 16".

1300 Attachment to SIR-O167, Rev. 1 20

90.

7U 0 0 o

800 300- -a--

I00.

_UpperVo wel 1500 in I0 -Bo-omHead 200-60 80 100 120 140 160 180 200 Minimum Reactor Vessel Metal Temperature (degrees F)

Figure 1 SSES-I Pressure Test P-T Curve (Curve A) for 35.7 EFPY Attachment to SIR 167, Rev. 1 21

130 1300 V

! **



/

I* i 1-

-t 7

1



I 4

1100.

1000 900 SW60

/,' I I

It1 -==

SX Im 0

a.

0 a

@2 0S 0

4..

C i

0.

I.

if 700 600 -

400 300-100 0

Upper Vatel

- BOttSW=

Head eltne

_I 200 60 eo 100 120 140 160 180 Minimum Reactor Vessel Metal Temperature (degrees F)

Figure 2 SSES-2 Pressure Test P-T Curve (Curve A) for 30.2 EFPY Attachment to SIR-O0-167, Rev. 1 22

700.#o@9Br Ea

_.Vessel 200.

, _.otom Hoad O.

60.0 eo.0 100.0 120.0 14.0 160.0 160.0 MimInum Reactor Vessel Metal Temperature (degrees F)

Figure 3 SSES-1 Core Not Critical Curve (Curve B) for 35.7 EF:PY Attachment toSIR- 00-167, Rev. I 23

I Za a0 a

I XX

7. 00 oo SDO

.d

,,=........

..=-

pper Vessel 200

_B ottom Had 100 60.0 80.0

-I-.0

-20.0

-40.0 160.0

-80.0 200.0 Mimlinum Reactor Vessel Metal Temperature (degrees F)

Figure 4 SSES-2 Core Not Critical Curve (Curve B) for 30.2 EFPY Attachment to SIR-00-167, Rev. 1 24

• 0 I-I 19 ftr aI-I 3

E 0

C.

1300 -

1200 1100 1000 700-400 300 200 Ina E_

_====I O 0.

0 80.0 100.0 120.0 140.0 160.0 180.0 Minimum Reactor Vessel Metal Temperature (degrees F) 200.0 Figure 5 SSES-1 Core Critical Curve (Curve C) for 35.7 EFPY Attachment to SIR-00-167, Rev. 1 25

0-.

0 I-I CLE S

A-80.0 100.0 120.0 140.0 160.0 180.0 Minimum Reactor Vessel Metal Temperature (degrees F)

Figure 6 SSES-2 Core Critical Curve (Curve C) for 30.2 EFPY 200.0 Attachment to SIR-00-167, Rev. I 26