View source for ST-HL-AE-1940, Forwards marked-up FSAR Pages Re Cumulative Usage Factor for Accumulator Safety Injection Lines & Pressurizer Surge Lines.Changes Support Preparation of SER & Will Be Incorporated Into FSAR Amend 59

{{Adams
| number = ML20212E782
| issue date = 03/02/1987
| title = Forwards marked-up FSAR Pages Re Cumulative Usage Factor for Accumulator Safety Injection Lines & Pressurizer Surge Lines.Changes Support Preparation of SER & Will Be Incorporated Into FSAR Amend 59
| author name = Wisenburg M
| author affiliation = HOUSTON LIGHTING &amp; POWER CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000498, 05000499
| license number = 
| contact person = 
| document report number = ST-HL-AE-1940, NUDOCS 8703040496
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 6
}}

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The Light NE                f Houston Lighting & Power P.O. Box 1700 Houston. Texas 77001 (713)228-9211 March 2, 1987 i                                                                     ST-HL-AE-1940 1
File No.: G9.1 10CFR50 f
l U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC      20555 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 Annotated FSAR Revisions Concerning Pipe Break Criteria

==References:==
(1) NRC Letter to HIAP, V. S. Noonan to J. H. Goldberg, December 31, 1986, ST-AE-HL-91085 (2) NRC Letter to HL&P, N. P. Kadambi to J. H. Goldberg, January 16, 1987, ST-AE-HL-91102 Enclosed are annotated revisions to the South Texas Project (STP) FSAR l        Section 3.6 concerning the cumulative usage factor for the accumulator safety injection lines and the pressurizer surge line. These changes are in response to references 1 and 2 above, are provided to support preparation of the SER,
!        and have previously been discussed between Mr. M. E. Powell (HL&P) and Mr. N. P. Kadambi (USNRC) . In addition, these changes will be incorporated as part of FSAR amendment 59.
l              If you should have any questions on this matter, please contact Mr.
M. E. Powell at (713) 993-1328.
l s
l M. R. Vi enburg Deputy P ject Man &g
(.
MEP/yd

==Attachment:==
Annotated Revisions to FSAR bection 3.6 0703040496 870302 PDR    ADOCK 05000498 g                   PDR _
Ll/NRC/au I
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File No.: G9.1 z liouston Lighting & Power Company                                                   Page 2:                '
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                        ' Regional Admintstrator, Region IV                               M.B.' Lee /J.E. Malaski~
Nuclear Regulatory _Commissi_on                                 - City of Austin-
                        -611 Ryan Plaza Drive, Suite 1000'                               -P.O. Box 1088; Arlington,LTX 76011.                                             Austin,-TX_ 78767-8814~
N. Prasad Kadambi, Project Manager                               M.T. Hardt/A'.' von Rosenberg:
U.S._ Nuclear Regulatory Commission.                             City Public Service ~ Board-
                                                                                                     ~
7920 Norfolk Avenue                                              P.O. Box 1771 Bethesda, MD- 20814                                              San Antonio, TX 78296
                                                              ~
                      - Robert L. Perch', Project Manager
                                                                                         - Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission                             ' U.S. Nuclear Regulatory Commission-7920-Norfolk Avenue-                                           - - -1717 H Street
:Bethesda, MD -20814                                              - Washington, DC - 20555
                      ' Dan R.' Carpenter iSenior Resident Inspector / Operations:
c/o U.S.~ Nuclear: Regulatory Commission P.O. Box 910 f               Bay City, TX 77414 Claude E. ' Johnson Senior Resident Inspector /STP
                        'c/o U.S. Nuclear Regulatory
: Commission-
                     !P.O. Box 910-Bay City, TX 77414
                     '-M.D.-Schwarz, Jr., Esquire
                      . Baker & Botts-
                     'One Shell" Plaza
                                   ~
Houston, TX' 77002 J.R. Newman,. Esquire Newman & Holtzinger, P.C.
1615'L1 Street,N.W.
Washington, DC 20036
,                        T.V.-Shockley/R.L. Range L                        Central Power & Light Company L                        r. O. Box 2121-Corpus Christi, TX 78403 Ll/NRC/au                                                                Revised 2/3/87 i,
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ST-HL AE-M40
                                                              'STP'FSARD               PAGE l 0F 4-y :.                                                                                                               ..
                                                                                                                 -40
                                        .'branchiintersection points are-considere'd a terminal end                 Q1l0.6
* for the branch line except;(1) where the branch and the
                                                                                                                     ,('l 57 main piping systems are model'ed in the same piping stress analysis and the branch line-is shown to have a signifi-
                                                                 ~
50.'
cant-effect on the main run behavior (i.e., the nominal                   Q110.6s size of-the branch line is at least one-half of that ofJ
_the main or the ratio of'the moment of inertia =of' main run-                .
_ pipe to the branch line is less than 10) or (2) where,.
regardless of size or moment of inertia ratio, the branch' lines are short in length and have no significant-                        57; restraint due to thermal expansion.
2)'    At intermediate' locations where the following conditions are satisfied.
a)     The maximum stress rcnge.between any two load sets,' deriv-ed on an elastically-calculated basis by-Equation (10) and
                                         'either Equations-(12) or (13) of subarticle NB-3653.of                    40-
;7                                        ASME Code Section III, under loadings associated with the OBE and normalgupset plangditions, er.ceeds 2.4 S,,.
                                                                           ?    $[f         .4Kb b)     The cumulative usage factor' exceeds'0.1 exceptn,.n       for 5h::
4-1--- -t--1 pip e -- n. .
                                          - 212-a . . . e.n t e < ,. .*
                   ~
7                     fluid :n;;;; ce..te..: ie ceetzell J .. J.. crit:d in ecriy 55 0                                        -5.2.3.2.1. ";ee'e ::: p:::aleted in euch piping d.::: Q
!!                                        c,    letive usag. fee;.:: ;;;::t        ^.S. u
: 2. ASME Code Section'III Class 2 and 3 piping,- breaks are postulated to oc.
j                     cur.at the following locations in each- run or branch run:
l-The terminal ends.
t
: a.                                                                                        40 t                     b. At all intermediate locations between terminal ends where the pri-mary plus secondary stresses'under normal and upset conditions and an OBE event, as calculated on an elastic basis by the sum of Equa-tions (9) and (10) (subarticle NC-3652 of the ASME Code,-Section III), exceed 0.8 (1.2SH + SA)*
* 55 l'              3. System Where a Combination of ASME Code Section III Class 1 and Class 2 High-energy Piping Exists l
In cases where both ASME Code Class 1 and Class 2 piping exist between 40 terminal ends, the following apply:
,                      a. If the stress levels and the cumulative usage factor in the ASME l
Code Class 1 portion and the stress levels in the Class 2 portion exceed the limits specified in 1. and 2. above, then the breaks are145 l                           postulated at each of these locations.                                              15 5
: 4. Non-nuclear High-energy Piping 40
: s. Breaks are postulated to occur in non-nuclear piping in the same                     Q110.07 I
manner as specified for ASME Code Section III Class 2 and 3 piping 3.6-9                            Amendment 57

    . vy ATTACHMEN ST-ML AE 19 PAGE J.OF
         -                                    Insert 1 for-Page 3.6-9 For the ' accumulator safety injection lines and the pressurizer surge line special analysis was completed and provided to the NRC by references 3.6-15 through 3.6-19. . Approval to delete specific postulated breaks for locations with a cumulative usage factor larger than 0.1 was obtained by reference 3.6-20.
4 f..
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  .r1       r-                                                                                                                                          -0 ATTACHMENT     .    .         .'
:STP FSAR .                           '          ST-HL-AE- IT'40    '-
         .                                                                                                                                                              PAGE 5 OF 't REFERENCES Section 3.6:                                                                                                                                                            N 3.6-1                                             " Pipe Breaks for the LOCA Analysis of the Westinghouse Primary Coolant Loop," WCAP-8082-P-A, (Proprietary)=and WCAP-8172-A_(Non-Proprietary), January 1975.
3.6-2                                             "SubcompartmentPressureAnalyses,"BN-TOP-4,-Rev.i, Bechtel Power Corporation, October 1977.
3.6-3                                            USNRC BTP MEB.3-1 Postulated: Break and Laakage Locations in Fluid System Piping Outside Containment.                                                    Branch Technical Position attached to SRP 3.6.2, November 24, 1975.
3.6-4                                            American Society of Mechanical Engineers,- Boiler and Pressure Vessel' Code, Section III, 1974 and 1975 Winter Addenda and other Addenda as. appropriate.
o3.6-5                                               " Design for Pipe Break Effects," Bechtel Power Corporation, BN-TOP-2, Revision 2,~ May'1974.
40
: 3. 6 - 6 ~-                                      Moody, F.       J.,          " Fluid Reaction and Impingement Loads." Paper presented at the ASCE Specialty Conference, Chicago, December 1973.
3.6 _7                                         ' "MULTIFLEX, A FORTRAN-IV Computer Program for Analyzing Thermal-Hydraulic-Structure System Dynamics," WCAP-8708 (Proprietary), February 1976, and WCAP-8709 (Non-Proprietary), February 1976.
3.6-8                                            " Documentation o_f Selected Westinghouse Structural Analysis Computer Codes," WCAP-8252, Revision 1, May 1977.
3.6-9                                           ANSI /ANS - 58.2, "American National Standard Design Basis-for Protection of Nuclear Power Plants Against Effects of Postulated Pipe Rupture," December-1980.
3.6-10                                          Bordelon, F.M., "A' Comprehensive Space-Time Dependent Analysis of Loss of Coolant (SATAN IV Digital Code)"                                                        45
: l.                                                                                  WCAP-7263, Proprietary (August 1971) and WCAP-7750,
(-                                                                                  Non-Proprietary (August 1971).
3.6-11                                           "PIPERUP" - Pipe Rupture Analysis Program, ME351, June 24, 1982.
49 3.6-12                                          Biggs, J.M., Introduction to Structural Dynamics, McGraw-Hill Book Company, New York 1964 3.6-13                                          NUREG/CR 2913, "Two Phase Jet Loads", dated January 1983.                                                           55
                         -3.6-14                                             " Technical Bases for Eliminating Large Primary Loop Pipe Ruptures as the Structural Design Basis for the South                                                             57 Texas Project", WCAP-10559, Proprietary (May 1984) and l-                                                                                  WCAP-10560, Non-Proprietary (May 1984).
[M.2                  c                        >                                                     3.6-24                                                 Amendment 57 B
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                 '   '                                                                              ATTACHMENT -
ST-HL-A E- l TN -
PAGELt OF + -
Insert 2 for Pg. 3.6-26                    e 3.6-15                           . Houston. Lighting & Power Company Letter to NRC, M. R. Wisenburg to H. L. Thompson, Jr. , February 28, 1986, ST-HL-AE-1611, 3.6-16                           . Houston Lighting ~& Power Company Letter to NRC, M. R. Wisenburg to V. S.~Noonan, September 17, 1986, ST-HL-AE-1758.
3.6-17                             " Cumulative Usage Factor Criterion for-Break Postulation for South Texas Units 1 and 2", WCAP-11327, Proprietary (October, 1986) and WCAP-11328, Non-proprietary (October,1986); submitted by Houston
                                                  -Lighting & Power Company Letter to NRC, M. R. Wisenburg to V.-S.
Noonan,.0ctober 31, 1986, ST-HL-AE-1793.                            .
3.6-18                             Houston Lighting & Power Company Letter to NRC, M. R. Wisenburg to
:V. S. Noonan, December 8, 1986, ST-HL-AE-1830.
3.6-19                             Houston Lighting & Power Company Letter to NRC, M. R. Wisenburg to V. S. Noonan, December-15, 1986, ST-HL-AE-1845.
               '3.6-20                             USNRC Letter-to Houston Lighting & Power Company, V. S. Noonan
:to J. H. Coldberg, December 31, 1986, ST-AE-HL-91085.
L1/NRC/au
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