View source for 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.

{{Adams
| number = ML052850302
| issue date = 10/05/2005
| title = 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.
| author name = Mckinney B
| author affiliation = PPL Susquehanna, LLC
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000387, 05000388
| license number = NPF-014, NPF-022
| contact person = 
| case reference number = PLA-5933
| document type = Letter type:PLA, License-Application for Facility Operating License (Amend/Renewal) DKT 50, Technical Specifications
| page count = 53
| project = 
| stage = Other
}}

=Text=
{{#Wiki_filter: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*--
v     .
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

MUZ) V-' I Limits  rr 1L FUE-v U 3.4.10 1300 1200i 1100 1000                                      --
co 00 Ca-900                                      I0 700
>0
: a. 600 0
IrI 50 400 400,                    ___                      BotUpper     d
             -    -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
     'U 800 77;
     &0 U'700 o 60no=-                                            -__=
    -I-500 00 3~00--
200 100 0
_     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
                                   /
I II II izuL 11  OC 100                      L            .
Sooo7
           &sect;00    -    -
      .T W
BOG4  -          _   _ _  _    __     _____             _   ____
0
     -1 I-n CD  700 .        -
Z0 (0
n 600_    -           =                                 =
U 0
c en 40                                                         --    Upper Vessel 40 SI 40  30        _ _ __ __Beltline
                                                                  .   -Bottom   Head 200        _l--
100 ..-.
60          80       100            120        140      160     180     21!00 Minimum Reactor Vessel Metal Temperature (degrees F)
Figure 3.4.10-1 System Hydrotest Limit with Fuel in Vessel (Curve A)
                                              ;           0o,z Eflf SUSQUEHAI NNA - UNIT 2                              TS /3.4-30                Amendmer nt 174&#xa2;,e

PPL Rev.A ikCS PTT Umfts 3.4.10 0-C" a
I                                                                           I.
m:
C.
0 I-in Gn 0
0 C-CK an 1CL a'   '                                   I      V       I 60      80     100    120      140    160     180    200 Minimum Reactor Vessel Metal Temperoture (degrees F)                   I I
Figure 3.4.10-2 Non-Nuclear Heating Limit (Curve B)
                                &a.-    d3oe z. t-PFi&deg;-l SUSQUEHANNA - UNIT 2                TS / 3.4-30a             Amendment 17t4',%

PPL Rev./'
RCS PIT Umits 3.4.10 0..
0.
a>   11
                                                                               . I to 0
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 . Q     v 0  L    I      II     l      __-  l          L 60   80     100    120         140  160   180      200 Minimum Reactor Vessel Metal Temperature (degrees F)
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
{&deg;  {'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 hours 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 hour 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(.      \/
fZe AA   kcit e  cup           42./.Iqc, Lo1                N(  Cclx/U~
A~        (fS^.t     eJX I VI hlt     443    3t'Vffff           1Jt4io  tALenre."(4111confinued)
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    &deg;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    &deg;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      &deg;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)             (&deg;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       &deg;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       &deg;F          > 30.2 EFPY Cooldown Rate =        100.0      &deg;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
                                                  &deg;,,     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&deg;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"
   #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}}