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 PPL Susquehanna, LLC %I I Sr. Vice President & Chief Nuclear Officer 769 Salem Boulevard Berwick, PA 18603 S $ S5.* 0 Tel. 570.542.3149 Fax 570.542.1504 btmckinney@pplweb.com PPl ;m*--

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pAl &A adl i 0 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" Docket Nos. 50-387 PLA-5933 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:

Attachment 1 - Proposed Technical Specification Changes (Mark-ups)

Attachment 2 - Proposed Technical Specification Bases Changes (Mark-ups)

Attachment 3 - 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.

Attachment 2 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.

Attachment 1 to PLA-5933 Proposed Technical Specification Changes (Markups)

3.4.10 rr. M u IL-r 0.

CL 40 800_L Q -~ Upper Vessel

.. ___ line d-A- Botborn Head 200 60 80 100 120 140 160 180 200 Minimum Reactor Vessel Metal Temperature (degrees F)

FIGURE 3.4.10-1 System Hydrotest Limit with Fuel in Vessel (Curve A)

SUSQUEHANNA- UNIT 1 TS 3.4-30 Amendment

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- -1 I II 60 80 100 120 140 160 180 Minimum Reactor Vessel Metal Temperature (degrees F)

Figure 3.4.10-2 Non-Nuclear Heating Limit (Curve B)

SQ TS.473Fa HAUI 1 Aed SUSQUEHANNA - UNIT 1 TS 3.4-30a Amendlment 2W

3.4.10

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_ 60 80 100 120 140 160 180 200 Minimum Reactor Vessel Metal Temperature (degrees F)

Figure 3.4.10-3 Nuclear (Core Critical) Umit (Curve C) 4r 3S. FefAy SUSQUEHANNA - UNIT 1 TS 3.4-30b Amendment 4e

PPL Rev. ;r RCS P/T Umits 3.4.10 1300 I

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Figure 3.4.10-1 System Hydrotest Limit with Fuel in Vessel (Curve A)

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PPL Rev.A ikCS PTT Umfts 3.4.10 0-C" a

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FIGURE 3.4.10-3 Nuclear (Core Critical) Limit (Curve C) t 30o, X Af SUSQUEHANNA - UNIT 2 TS / 3.4-30b AAkmendment 174AW

Attachment 2 to PLA-5933 Proposed Technical Specification Bases Changes (Markups)

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. C/f ) B-k~a$q9 g Ve.arie V144 es I.(,1 >. "Cl iJ" 4fs kk5-.--l QIIL zA~vi~ vve.th^,ot4 1 1ol,,. I j J12 c 4y foPevele a&.*te meeA eI SUSUEH N T2.UNITB 1,.4"4)J Ron 2

{° {'DtPr0 c giprOVtef Vfjfel Ajets" JR W4ec(f,10(Jr')(oontinued)

SUSQUEHANA - UNIT 1 TS l B 3.4-49 Revision 2

RCS P/T Umits B 3.4.10 7Wi

, > BASES V t3BACKGROUND The P/T limit curves are composite curves established by superimposing

- ^- 4 (continued) 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.

t4' 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 dI A,,.

,g X ~~.L APPLICABLE The P/T limits are not derived from Design Basis Accident (DBA) analyses.

They are prescribed during normal operation to avoid encountering pressure,

~ ~ ANALYSES 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.

. dt f; de 61 " I 19o, fv'd Zoo I r& g4zm. 7 4. .4 r SUSQUEHANNA - UNIT 1 TS I B 3.4-57 Revision 2

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 T,/- Bj 3.Revisi SUSQUIAN UNIT 2 h_ o n 2 neck>>Blanc atll a {((f~c;>ed ,;l Wle Y3(. \/

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

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

'C RCS P/T ULmits B 3.4.10 BASES Q A BACKG ROUND The P/T limit curves are composite curves established by superimposing (contir oed) 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

,sf ri 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 4-- 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 3e the location of the tensile stress between the outer and inner walls.

iwJ 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.

4-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. -

- @EAPPLICD\BLE The PIT limits are not derived from Design Basis Accident (DBA) analyses.

tatY SAETY They are prescribed during normal operation to avoid encountering pressure, ANALYS;ES 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

- i .J 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.

) 3 3 j 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, "Studyto 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

Attachment 3 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: _

Gary Stevens, P. E.

ok Reviewed By:t 1/

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 = correction factor, calculated to consider the nonlinear.

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

Kin = secondary membrane stress intensity factor

= Mm*Osm Klb = 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 I, 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) where: F(a/r.) = nozzle stress factor, from Figure A5-1 of [5]

Upm = primary membrane stress R = correction factor, defined above aypb = primary bending stress a = 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/ 4 1), 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]:

ForPressureTest 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 + 90 0F.

• 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 + 60 0F. This limit has been a standard recommendation for the BWR industry for non-ductile failure protection.

ForCore Not CriticalConditions(Curve B):

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

• 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 CriticalConditions (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 0

closure flange region temperature (ARTNmr + 60 F) 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 + 40 0F, 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 = SSES-1 Component = Beltine Vessel thickness, t = 6.1875 inches, so 4Jt- 2.487 iAnch Vessel Radius, R = 126.6875 inches ARTNDT = 61.4 OF _-> 35.7 EFPY K", = 0.0 ksiinchl" ATIMI2 = 0.0 'F (no thermal for pressure test)

Safety Factor = 1.5 {for pressure test)

Mm= 2.303 I,

Temperature Adjustment = 0.0 Pressure Adjustment = 30 psig (hydrostatic pressure for a full vessel)

Hydro Test Pressure = 1,563 psig Flange RTNDT = 10.0 OF Fluid Calculated Adjusted Adjusted Temperature 114t Pressure Temperature Pressure for T Temperature Kic Kip P for P-T Curve P-T Curve 2

(F) (en Jksrlnch" ) (ksl*inch 2) (Pslg) (7F) (psig) 70 .0 70 70 57.83 38.55 817 70 787 75 75 60.42 40.28 854 75 824 80 80 63.28 42.18 894 80 864 85 85 66.44 44.29 939 85 909 90 90 69.94 46.62 989 90 959 95 95 73.80 49.20 1043 95 1,013 100 100 78.07 52.05 1104 100 1,074 105 105 82.79 55.19 1170 105 1,140 110 110 88.00 58.67 1244 110 1,214 115 115 93.77 62.51 1325 115 1,295 120 120 100.14 66.76 1416 120 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 = SSES-2 Component = Beitline Vessel thickness, t = 6.1875 inches, so 4! 2.487 finch Vessel Radius, R = 126.6875 inches .

ARTNDT = 46.7 OF > 302 EFPY 2

K,, = 0.0 ksi*inch" ATIMIx = 0.0 °F (no thermal for pressure test)

Safety Factor = 1.5 (for pressure test)

Mm= 2.303 Temperature Aclustment = . 0.0 OF Pressure Adjustment = 30 psig (hydrostatic pressure for a full vessel)

Hydro Test Pressure = 1,583 psig Flange RTT = 10.0 °F Fluid Calculated Adjusted Adjusted Temperature 1/4t Pressure Temperature Pressure for T Temperature Kic Kip p for P-T Curve P-T Curve (F) (OF) (ksl*inch 2) (kslinch"2) (PSlg) (7F) (pslg) -

70 0 70

• 70 66.24 44.16 936 70 906 75 75 69.72 46.48 986 75 956 80 80 73.56 49.04 1040 80 1,010 85 85 77.80 51.87 1100 85 1,070 90 90 82.49 55.00 1166 90 1,136 95 95 87.68 58.45 1239 95 1,209 100 100 93.41 62.27 1320 100 1,290 105 105* 99.74 66.49 1410 105 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 = SSES-1 Component = Upper Vessel (based on FW nozzle)

ARTNDT = 40.0 'F -- -> All EFPY Vessel thickness, t = 6.5 inches, so 4t 2.55 Ainch Vessel Radius, R = 126.7 inches F(a/m) = 1.6 nozzle stress factor Crack Depth, a = 1.63 inches Safety Factor = 1.5 Temperature Adjustment = 0.0 pF Pressure Adjustment = 0.0 psig Unit Pressure = 1,563 psig Flange RTNDT = 10.0 OF Fluid Calculated Adjusted Adjusted Temperature 114t Pressure Temperature Pressure for T Temperature Kic Kip P for P-T Curve P-T Curve

(*F) (ksl*inch") (ksl~inch 112 )

. a (oslap (70) (psig) 70 0 70 312.5 100 312.5 0 0 42.52 28.34 402 100 402 10 10 44.58 29.72 421 100 421 20 20 47.10 31.40 445 100 445 30 30 50.18 33.45 474 100 474 40 40 53.93 35.96 509 100 509 50 50 58.52 39.02 553 100 553 60 60 64.13 42.75 606 '100 606 70 70 70.98 47.32 670 100 670 80 80 79.34 52.90 750 100 750 90 90 89.56 59.71 846 100 846 100 100 102.04 68.03 964 100 964 110 110 117.28 78.19 1108 110 1108 120 120 135.90 90.60 1284 120 1284 130 130 158.63 105.76 1498 130 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 = 30.0 Vessel thickness, t = 6.5 inches, so 4t 2.55 Anch.

Vessel Radius, R = 126.7 inches F(a/m) = 1.6 nozzle stress factor Crack Depth, a = 1.63 inches Safety Factor = 1.5 Temperature Adjustment = 0.0 pF I1 Pressure Adjustment = 0.0 psig Unit Pressure = 1,563 psig Flange RTNDT = 10.0 OF Fluid Calculated Adjusted Adjusted Temperature !114 Pressure Temperature Pressure for T Temperature Kic Kip P for P-T. Curve P-T Curve (OF) ('F) (kslinchWm) (ksl*inchI 2) (psig) (IF) (psig) 70 '0 70 312.5 100 312.5 0 0 44.58 29.72 421 100 421 10 10 47.10 31.40 445 100 445 20 20 50.18 33.45 474 100 474 30 30 53.93 35.96 509 100 509 40 40 58.52 39.02 553 100 553 50 50 64.13 42.75 606 100 606 60 60 70.98 47.32 670 100 670 70 70 79.34 52.90 750 100 750 80 80 89.56 59.71 846 100 846 90 90 102.04 68.03 964 100 964 100 100 117.28 78.19 1108 100 1108 110 110 135.90 90.60 1284 110 1284 120 120 158.63 105.76 1498 120 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 Polard = SSES-1 Compon,erg = Bottom Head Vessel thicknes s. t = 6.1875 inches, so 4t 2.A7 AJinch Vessel Radlu ;, R= 126.6875 Inches ARTINMT= 34.0 All EFPY 2

Kg = 0.0 ksi-inch' rl/= 0.0 °F (no thermal for pressure test)

Safety Facttor= 1.5 (for pressure test)

Stress Concentration Fac tor = 3.0 Bottom head penetrations WmI= 2.303 Temperature Adjustmi 3rn = 0.0 OF Heighli of Water for a Ful Vessel = 882.0 Inches Pressure Adjustnx rit = 31.85 psig Oydostafic pessixe at bottom head bra aA Usael at 706F)

Hydro Test Pressuure= 1,563 psig Flange Rlrprwr= 10.0 Fluid Calculated Adjusted Adjusted Temperature 1/4t Pressure Temperature Pressure fr T Temperature Kic Kip p for P-T Curve P-T Curve 2

(T) (°F) (ksl*inchm ) (ksl*inchr) J2~b) (OF) (Pat) 70 0 70 70 75.80 50.53 714 70 682 75 75 80.28 5352 757 75 725 80 80 85.23 56.82 803 80 771 85 85 90.70 60A7 855 85 823 90 90 96.75 64.50 912 90 880 95 95 103.43 6825 975 95 943 100 100 110.82 73.88 1044 100 1,012 105 105 118.98 79.32 1121 105 1,089 110 110 128.00 85.33 1206 110 1,174 115 115 137.97 91.98 1300 115 1,268 120 120 148.99 9933 1404 120 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 = SSES-2 Component = Bottom Head Vessel thickness, t = 6.1875 Inches, so 4t 2.487 Ainch Vessel Radius, R = 1266875 Inches ARTwT = 24.0 °F > All EFPY Kk = 0.0 ksi*InchII

,TIN = 0.0 IF (no thermal for pressure test)

Safety Factor = 1.5 (for pressure test)

Stress Concertration Factor = 3.0 Bottom head penetrations I.

Mm= 2.303 Temperature Adjustment = 0.0 Height of Water for a Full Vessel = 882.0 Inches Pressure Adjustment = 31.85 psig (hydrostatic pressure at bottom head for a kill eael at 70F)

Hydro Test Pressure = 1,563 psig Flange RTwT = 10.0 eF Fluid Calculated Adjusted Adjusted Temperature 114t Pressure Temperature Pressure for T Temperature Kic Kip p for P-T Curve P-T Curve (F) CFp) (kslinch"2 ) (ksrinchla) (psig) (F) (psig) 70 0 70 70 85.23 56.82 803 70 771 75 75 90.70 60.47 855 75 823 80 80 96.75 64.50 912 80 880 85 85 103.43 68.95 975 85 943 90 90 110.82 73.88 1044 90 1,012 95 95 118.98 79.32 1121 95 1,089 100 100 128.00 85.33 1206 100 1,174

• 105 105 137.97 91.98 1300 105 1268 110 110 148.99 99.33 1404 110 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 = SSES-1 Component = Beltline Vessel thickness, t = 6.1875 inches, so -At 2.487 4inch Vessel Radius, R = 126.6875 inches ARTNM = 61.4 OF  :> 35.7 EFPY Cooldown Rate = 100.0 eF/hr Kit= 9.08 ksl*inchll 2 Safety Factor = 2.0 Mm= 2.303 Temperature Adjustment = 0.0 Pressure Adjustment = 30.0 psig (hydrostatic pressure for a full vessel)

Flange RTwT = 10.0 OF Fluid Calculated Adjusted Adjusted Temperature 1/4t Pressure Temperature Pressure for T Temperature Klc Kip P for P-T Curve P-T Curve (F) (F) (ksl*lnch' 2 ) (ksrinch' 2) (psig) (eF) (psig) 70 0 70 70.0 57.83 24.37 517 70 487 75 75.0 60.42 25.67 544 75 514 80 80.0 63.28 27.10 575 80 545 85 85.0 66.44 28.68 608 85 578 90 90.0 69.94 30.43 645 90 615 95 95.0 73.80 32.36 686 95 656 100 100.0 78.07 34.50 731 100 701 105 105.0 82.79 36.86 782 105 752 110 110.0 88.00 39A6 837 110 807 115 115.0 93.77 42.35 898 115 868 120 120.0 100.14 45.53 965 120 935 125 125.0 107.18 49.05 1040 125 1010 130 130.0 114.96 52.94 1123 130 1093 135 135.0 123.56 57.24 1214 135 1184 140 140.0 133.06 61.99 1314 140 1284 145 145.0 143.56 67.24 1426 145 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 = SSES-2 Component = Beltline Vessel thickness, t = 6.1875 inches, so 4t 2.487 Inch Vessel Radius, R = 126.6875 inches ARTNDT = 46.7 °F > 30.2 EFPY Cooldown Rate = 100.0 °F/hr K%= 9.08 ksi*inch" 2 Safety Factor = 2.0 Mm = 2.303 I.

Temperature Adjustment = 0.0 pF (

Pressure Adjustment = 30.0 psig (hydrostatic pressure for a full vessel)

Flange RTNDT = 10.0 Fluid Calculated Adjusted Adjusted Temperature 1/4t Pressure Temperature Pressure for T Temperature KIc Kip P for P-T Curve P-T Curve (F) (OF) (ksPinch" 1) (ksl*lnch" 2 ) (psig) (OF) (ps1g) 70 0 70 70.0 66.24 28.58 606 70 576 75 75.0 69.72 30.32 643 75 613 80 80.0 73.56 32.24 684 80 654 85 85.0 77.80 34.36 729 85 699 90 90.0 82.49 36.71 778 90 748 95 95.0 87.68 39.30 833 95 803 100 100.0 93.41 42.17 894 100 864 105 105.0 99.74 45.33 961 105 931 110 110.0 106.74 48.83 1035 110 1005 115 115.0 114.47 52.70 1117 115 1087 120 120.0 123.02 56.97 1208 120 1178 125 125.0 132.46 61.69 1308 125 1278 130 130.0 142.90 66.91 1419 130 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, - 40.0 T - AN EFPY

20. k O 1050 psig am. 022 hal 1050 psig Pase TeMP 1.119 ki O 546 F 0 .F 1S.4 kalO 546 F 00 F 45.0 hal os..

2.4 Safety Factor . z.

F(afrj - 18 Tenmperatsa A4uatrrent - 0.0 *F 1.

Presswe Adjustmet = 0L. pat Hydro Teoo Pressure . 1563 psig Range RTCT - 10.0 *F Calculsted Adft AcQuatd Total Terrpemure Tomperaw,. Pressure for Pressure saturation a.. a. Gew Klt lap ac br P-TCuv P-T Curve P Teeratuwre 9Pb a fpsQ tksO) A Ikslnchn) W chu) (klwnch" ff) Ipsig 70.0 0 0.98 0.01 7.36 8.65 17.00 23.3 32 41.0 0.0 50 297.3 1wo0 1.95 0.02 8.79 10.34 21.11 1.00 39.6 7.7 55.1 0.0 70. 100 100 237.7 64.0 2.93 0.03 9.79 11.52 2427 44.3 11.5 67.3 70.0 150 150 3S5.8 324 QC03 10.06 1183 25.16 455 12.7 71.0 70.0 70. 166 185.9 373.4 1.00 3.90 0.04 110.5 12A4 26.96 47.9 15.3 78. 79.1 79.1 200 200 367.9 1.00 4.88 0.05 11.23 1320 29.36 60.8 192 88.1 88.6 MI 250 250 40K.2 1.00 422.1 5.85 Q0. 11.79 13.86 21.57 53.3 23.0 994 98.0 O80 300 3SO 1.00 6.10 0.07 11.92 14.02 32.10 53.9 24.0 101.9 58.9 o99 312.5 312.5 425.7 1.00 425.7 6.10 0.0 11.92 14.02 32..10 63.9 24.0 019 99.9 130.0 812.5 312.5 1.00 6.113 0.07 12.28 14.45 33.63 55.6 26.8 109.3 105.0 120.0 350 350 436.0 1.00 7.81 o0e 12.73 14.97 35.59 57.6 30.7 118.s 111.0 120.0 400 400 448.5 1.00 6.78 0.0 13.13 15.4S 37.45 59.4 4.5 1284 116.2 1201 450 450 4599 1.00 9.76 0.10 13.51 158M 3925 1.00 61.1 28.3 137.8 120.0 10.0 500 5W 470.4 1.00 10.73 0.12 13.85 16.2 40.99 1.O 62.7 42.2 147.0 125.1 130.0 550 550 480.1 11.71 0.13 14.17 16.7 42.67 1.00 64.1 46.0 156.1 129.0 600 489.1 t11. 0.13 1426 16.77 43.13 1.00 10.8 64.5 47.1 15s.7 130.0 130.0 614 614 491.6 12.68 0.14 14.47 17.02 44.31 65.5 49.9 1652 132.5 132.5 650 650 497.

13.68 0.15 14.76 1735 45.92 0.80 o0.7 64.9 53.7 172.3 185.2 152 700 5057 750 14.64 0.16 15.03 17A7 47.49 0.93 63.0 57.5 178.0 137.2 1372 7oo 5132 15.61 0.17 1523 17.7 4SM IM 61.1 61.3 183.6 138.1 139.1 S00 800 520.4 16.5S 0.18 1S.3 18.26 50.55 O0.4 59.1 85.1 189.3 140.9 148.9 8450 850 527.3 WOO 17.56 0.19 15.76 18.53 52.04 572 68.9 195.0 142.7 12.7 OS 33.9 950 540.1 18.54 020 1S.8 1E6.0 53.52 0.76 0.86 OAS 55.3 72.7 200.6 1444 144A 950 19.51 0.21 1620 19.0S 54S7 0.63 0.73 53A 76.5 206.3 146.1 1461 1000 1000 546.2 204S 022 16.40 1029 56.40 0.69 514 80.3 212.0 147.7 147.7 1050 1050 552.0 21.47 023 16.60 19.52 57.82 49.5 84.1 217A 149.3 149.3 1100 1100 557.8 22.44 024 16.79 19.75 5923 47.6 87.6 223.3 150.8 150. 1150 1150 563.0 23.42 025 16s9 19.97 60.62 0.59 45.6 91.6 228.9 152.2 1522 1200 1200 5682 1153.7 24.39 026 17.16 20.18 e1.99 0.56 43.7 95.4 234.6 15.7 1250 1250 573.3 25.37 027 17.3 20.38 63.36 0.53 41.6 99.2 2402 155.0 1550 1300 1300 578.2 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 HydroText 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 5 (Palo)

(P9al) m () Owl) fka) &&Q &80 R ks ch' (kswhn (k*knwh5 () RF

- - - 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 4062 4.88 O.5 1123 13.20 29.36 1.00 50.8 19.2 9.1 79.6 79 250 250 422.1 .5.85 0.06 11.79 136 31.57 1.00 53.3 23.0 994 88.0 I0 30 300 312.5 425.7 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 438o 6.83 07 1228 14,45 m3 1.00 55.6 .268 100.3 95.0 130.0 350 350 4483 7.81 008 12.73 147 35.5 1.00 67. 30.7 118. 101.0 130.0 400 400 4599 6.73 0.09 13 15A.5 37A5 1.00 80.4 34.5 128.4 1082 130.0 450 450 500 4704 9.76 0.10 13.51 158 39.25 1.00 61.1 38.3 137.0 110.9 10.o soo 4I 10.73 0.32 13.5 1629 40.99 1.00 62.7 422 147.0 115.1 130.0 S50 55C 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 505.6 13.86 0.15 14.76 17.35 45.92 0t7 64. 53.7 172.3 1252 130.0 700 700 5132 14.64 0.16 15.03 17.67 47.9 033 83.0 57.5 178.0 127.2 13.0 750 750 757 514. 14.77 0.16 15.06 17.71 47.71 032 82.7 58.0 178.7 127A 13. 757 5204 15.61 0.17 1526 1737 49.03 O08 61.1 61.3 183.6 129.1 130.0 80 So 823. 16.10 0.17 15A1 18.12 40.79 0.86 80.1 632 186.5 130.0 13.0 825 825 5273 168 0.18 15.8 18.26 50.55 0.84 59.1 65.1 189.3 130.9 10 850 850 900 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 552.0 20.49 0.22 1640 1929 56.40 0.69 51.4 0.3 212.0 137.7 137.7 1050 1050 557.6 21.47 023 16.0 19.2 57.82 0.86 495 84.1 217. 139.3 1i31 1100 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 = SSES-1 Component = Bottom Head (Penetrations Portion)

Vessel thickness, t = 6.1875 inches, so 4t 2.487 'inch Vessel Radius, R = 126.6875 inches Cooldown Rate = 100.0 'F/hr Safety Factor = 2.0 Stress Concentration Factor = 3.0 ARTN,,T = 34.0 OF- ===> All EFPY Mm= 2.303 Kft= 9.08 ksl*inchll 2 I.

Temperature Adjustment = 0.00 OF Height of full vessel = 882.0 inches Pressure Adjustment = 31.85 psig Unit Pressure = - 1563 psig Flange RTNDT = 10.0 OF Fluid Calculated Adjusted Adjusted Temperature 114t Pressure Temperature Pressure for T Temperature Kic Kip P for P-T Curve *P-T Curve 1*F1 (eF1 (ks*linch"2) (ksl*lnchl 2 ) (psig) -

(7F) (Psig)

- --- L-A 70 0 70.0 75.80 33.36 472 70 440 70 75 75.0 80.28 35.60 503 75 471 80 80.0 85.23 38.08 538 80 506 85 85.0 90.70 40.81 577 85 545 90 90.0 96.75 43.84 620 90 588 95 95.0 103.43 47.18 667 95 635 100 100.0 110.82 50.87 719 100 687 105 105.0 118.98 54.95 777 105 745 110 110.0 128.00 59.46 841 110 809 115 115.0 137.97 64.45 911 115 879 120 120.0 148.99 69.96 989 120 957 125 125.0 161.17 76.05 1075 125 1043 130 130.0 174.63 82.78 1170 130 1138 135 135.0 189.50 90.21 1275 135 1243 140 140.0 205.94 98.43 1391 140 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 = SSES-2 Component = Bottom Head (Penetrationr Portion)

Vessel thickness, t = 6.1875 inches, so At 2.487 4inch Vessel Radius, R = 126.6875 inches Cooldown Rate = 100.0 'F/hr Safety Factor = 2.0 Stress Concentration Factor = 3.0 ARTNOT = 24.0 OF ====-> All EFPY Mm = 2.303 1C, = 9.08 ksi'inch12 Temperature Adjustment = 0.00 OF Height of full vessel = 882.0 inches Pressure Adjustment = 31.85 psig Unit Pressure = 1563 psig Flange RTNDT = 10.0 eF Fluid Calculated Adjusted Adjusted 114t Pressure Temperature Pressure for Temperature T Temperature Kic Klp P lor P-T Curve P-T Curve (eF) (F) (ksl-inchl" (ksi*lnchl m) (pslg) (eF) -

(pslg) 70 0 70 70.0 85.23 38.08 538 70 506 75 75.0 90.70 40.81 577 75 545 80 80.0 96.75 43.84 620 80 588 85 85.0 103.43 47.18 667 85 635 90 90.0 110.82 50.87 719 90 687 95 95.0 118.98 54.95 777 95 745 100 100.0 128.00 59.46 841 100 809 105 105.0 137.97 64.45 911 105 879 110 110.0 148.99 69.96 989 110 957 115 115.0 161.17 76.05 1075 115 1043 120 120.0 174.63 82.78 1170 120 1138 125 125.0 189.50 90.21 1275 125 1243 130 130.0 205.94 98.43 1391 130 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 g F 90 c, - 45.0 kWi M.,. 2.64 Safety FacorW 2.0 F(ar,,) 1.6 Temperture A4ustment- 0.0 IF Pressure Adjustment 0.0 ps1g I.

Hydro Test Pressure 1563 pig Flange RTMT 10.0 IF Calculated Adjustd Adjusted Pressure Saturation Total Temperature Temperature Pressure for P Temperature Ip= @p cam 6muw Klt Kip Kbc T for P-T Cune P-T Curve (rF) (ksl) (kal) (ksl) (ksl) (ks$ R ;srlnchWkwhchrkxrkbch- ( 5F) (Psal) 0 7 0.0 80 297.3 0.98 0.01 7.86 8.85 17.00 1.00 33.8 8.8 41.0 70.0 60 81.4 S24.7 1.89 0.02 8.83 9.80 19.78 1.00 37.7 62 802 30.0 700 e1 100 337.7 1.95 0.02 8.79 10.84 21.11 1.00 89.8 7.7 85.1 42.8 a. 100 tOO .93 0.03 9.79 11.52 2427 1.00 44. 11t. 67. 64.9 104. 150 150 865.8 200 887.9 8.90 0.04 10.88 12.44 26.96 1.00 47.9 18.8 78.5 79.1 l19. 200 250 4062 4.880 0 1123 18.20 29.8 1.00 60.8 192 89.1 89.6 129.6, 250 SOO 422.1 6.5 0.06 11.79 1.86 81.87 1.00 88.3 23.0 99.4 98.0 138. SOO 812.8 425.7 6.10 O 11.92 14.02 82.10 1.00 88.9 24.0 101.9 99.9 1t 812.8 S12.5 425.7 6.10 0.07 11.92 14.02 82.10 1.00 88.9 24.0 101.9 99.9 1nu. 812.8 S50 436.0 .83 O0 12.28 14A.5 3.63 1.00 85.6 268. 109.8 105.0 1t 40 400 448.5 7.1 0.08 12.73 14.97 85.89 1.00 67.6 80.7 118.9 111.0 1N. 400 450 459.9 8.78 Q09 t13t 15.45 87.45 1.00 89.4 34.8 128.4 116.2 17C0 450 800 470.4 9.76 Q010 18.1 18.88 3925 1.00 61.1 88.8 187. 120.9 170.0 8CO 850 480.1 10.73 0.12 18.85 1629 40.99 1.00 62.7 42.2 147.0 125.1 170.0 50 600 489.1 11.71 0.18 14.17 16.67 42.67 1.00 64.1 46.0 156.1 129.0 17.0 600 614 491.6 11.98 0.13 14.26 16.77 48.1S 1.00 64.5 47.1 158.7 180.0 170.0 614 650 497.6 12.68 0.14 14.47 17.02 44.81 1.00 e5.6 49.9 1652 182.5 1725 650 7Wo 506.6 18.66 0.15 14.76 175 45.92 0.97 64.9 837 172.8 185.2 1782 700 750 513.2 14.64 0.16 18.08 17.67 47.4S 0.93 63.0 87.6 178.0 1S7.2 1772 780 8oo 820.4 15.61 Q17 1828 17.97 49.03 0.88 61.1 61.8 183.6 139.1 179.1 So 850 827.8 16.9 0.18 15.S81826 80.65 0.84 89.1 65.1 189.8 140.9 1809 850 900 633.9 17.86 0.19 18.76 18.88 62.04 0.80 672 88.9 195.0 142.7 182.7 900 950 840.1 1654 020 15.98 18.80 68.52 0.76 85.8 72.7 200.6 144.4 184.4 950 1000 64.2 19.8 021 1620 19.05 54.97 0.73 63.4 76.8 206.8 146.1 8661 1000 1050 852.0 20.4S 022 16.40 1929 56.40 0.69 81.4 80. 212.0 147.7 187.7 1050 1100 857.6 21.47 0.23 16.60 19.82 67.82 066 49.5 84.1 217.6 149.. 189.8 1100 1180 883o 22.44 024 16.79 19.75 6923 0.63 47.6 87. 223.8 150.8 190. 1180 1200 88.2 23.42 025 1698 19.97 60.62 0.8 45.6 91.6 228.9 152.2 192 1200 1250 87S.8 24.89 026 17.16 20.18 61.99 0.8 43.7 95.4 284.6 183.7 193.7 1250 1300 8762 25.87 027 17.8 20.8 63.86 0. 41.8 992 2402 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 khi 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 TenmeruaureAdustrmet

• 0.0 F Pressae Adjustment. 0.0 psig

'Hydro Test Presu e. 1t63 psd Flange RTmT

• 10.0 *F Colculated "uded Adjustd Pressure aturation Tows TemPersture Temperetwr Pressure for P T"Vare ap. ab 6 Gb KIt l0P Kkc T IorP.TCum P-T Curv, ab"

1. wsb) mF) &SOc (tksl &s) 0) R - silnch'slst"tnch"N

70. 0 80 2s7.3 098 0.01 7.36 .a8s 17.00 1.00 33.3 3.8 41.0 - 700 so 1.86 0.02 6.69 10.22 20.71 1.00 39.3 7.3 54.0 30.0 7M0 96

95. 334.7 100 337.7 1.95 0.02 679 1034 21.11 1.0 39. 7.7 55.1 32.8 72 100 2.3 0.03 9.79 11.52 2427 1.00 44.3 11.5 673 64.

I49 150 180 385.8 200 387.9 3890 0.04 10.8 12.44 26.6 l.00 47.9 15.3 78.5 69.1 109.1 200 250 4062 4.68 0.05 1123 1320 29.38 1.00 50.8 192 89.1 79.6 11. 250 8.65 0.06 11.79 13*8 3157 1.00 53.3 23.0 9G.4 88.0 125.0 300 300 422.1 312.5 425.7 6.10 0.07 1192 14.02 32.10 1.00 53.9 24.0 101.9 60.9 129. 312.5 312.5 425.7 6.10 0.07 11.92 14.02 32.10 1.00 53.9 24.0 101.0 6s9. 70 312.5 436.0 6.3 0.07 1228 14.45 3363 1.00 85.6 26.8 109.3 05.0 1m 350 350 400 448.5 7J1 0.08 12.73 14.97 35.58 1.00 57.6 30.7 e1.9 101.0 11U 400 459. 6.78 0o.9 13.13 15.4s 37.45 10 89A4 34.5 128.4 106.2 W3. 450 450 500 470.4 0.76 0.10 13.1 15.68 39.25 1.00 61.1 38.3 137. 110.9 1.0 S00 480.1 10.73 0.12 13.5 16.29 4099 1.00 62.7 42.2 147.0 115.1 MAon 550 550 4B8.1 11.71 0.13 14.17 16.67 42.67 1.00 64.1 48.0 156.1 11.0 170.0 600 600 497.6 12.6 4.14 14.47 17.02 44.31 1.00 65.5 499 165.2 122.5 170.0 50 650 505.6 13.6 0.15 14.76 17.35 45.92 0W7 54.9 .53.7 172.3 125.2 170.0 700 700 750 513.2 14.64 O.16 15.03 17.67 4749 0.93 63.0 57.5 178.0 127.2 170. 750 757 514.3 14.77 0.16 15.06 17.71 47.71 0.92 62.7 58.0 178.7 127A 170. 757 520.4 15.61 0.17 1528 17.7 49.03 0.68 61.1 61.3 183.6 129.1 170.0 a00 W00 825 523.0 16.10 0.17. 15.41 1L812 49.79 0.66 60.1 63.2 186.5 130.0 170.0 825 850 527.3 1659 0.16 15.83 18.26 s0.55 0.84 59.1 6.1 189.3 130.9 170 850 533.9 175 0.19 15.76 18.53 52.04 0.60 572 68s 1950 132.7 172.7 900 9X0 950 840.1 16.54 0.20 15.88 18.80 53.52 0.76 55.3 72.7 200. 134A4 174.4 950 1000 5462 19.51. 021 1620 19.05 5497 0.73 53.4 76.5 206.3 136.1 176.1 1000 1050 S52.0 20.4S 0.22 16.40 1929 568.O 0.69 S1A 80.3 212.0 137.7 7.7 1050 557.6 21.47 0.23 16.60 19.82 57.82 0.66 49.5 84.1 217.6 13932 179.3 1100 1100 1150 563.0 22.44 0.24 16.79 19.75 59.23 0.63 476 67. 2233 140.6 160.6 1150 1200 86E2 23.42 0.25 168 19.97 60.62 O05 45.6 91.6 228.0 142.2 162.2 1200 573.3 24.39 026 17.16 20.18 6199 O.6 43.7 95.4 234.6 143.7 163.7 1250 1250 1300 578.2 25.37 027 17.33 20.38 63.38 O03 41.8 99.2 2402 145.0 16". 1300 Attachment to SIR-O167, Rev. 1 20

90.

00 7U o 800 I00.

300- -a-- --

1500 in

- _UpperVo wel 200-I0 -Bo-omHead 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  ! **

• Ii 1- -t 7

/ 1 I 4 I

1100.

/,'

1000 I

I.

900 Im SX 0 -== It1 SW60 if a.

0

@2 700 -

0 S

0a 600 - --

4..

C i

400 - -

0.

300-

- - Upper Vatel 100 - - BOttSW= Head

. eltne

_I ....

0 _ _

eo 100 120 140 160 180 200 60 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

Ea 700 .#o@9Br

. '._ _.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 XX I 7.00 ---

oo SDO .d .......

.,,=. . .=-

. . . . . pper Vessel 200 _B - ottomHad _

100 60.0 80.0 -I-.0 -40.0

-20.0

-80.0 160.0 200.0 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

1300 -

1200 1100

• 0 1000 I-I I-a 700-ftr 19 I

3 E

400 0

C.

300 200 Ina O0. E_80.0 100.0

_====I 120.0 140.0 160.0 180.0 200.0 0

Minimum Reactor Vessel Metal Temperature (degrees F)

Figure 5 SSES-1 Core Critical Curve (Curve C) for 35.7 EFPY Attachment to SIR-00-167, Rev. 1 25

I-0-.

0 I

CL E

S A-80.0 100.0 120.0 140.0 160.0 180.0 200.0 Minimum Reactor Vessel Metal Temperature (degrees F)

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