ML20205T604
| ML20205T604 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 11/07/1988 |
| From: | Malloy M NRC OFFICE OF SPECIAL PROJECTS |
| To: | NRC OFFICE OF SPECIAL PROJECTS |
| References | |
| IEIN-86-011, IEIN-86-11, NUDOCS 8811140304 | |
| Download: ML20205T604 (65) | |
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Novemb,er 7,1988 Docket Hos. 50-445 and 50-446 APPLICANT:
Texas Utilities Electric Company (TV Electric)
FACILITY:
Comanche Peak Steam Electric Station (CPSES), Units 1 and 2
SUBJECT:
SUMMARY
OF MEETING ON SEPTEMBER 29, 1988 - DISCUSSION OF THE PLANT SYSTEMS BRANCH'S FSAR REVIEW FOR COMANCHE PEAK NRC staff and representatives of TU Electric met on "er ' ember 29,)1988 in Rockville, Maryland to discuss the Plant Systems Brm.. e's (SPLB's ongoing review of changes to the Comanche Peak Final Safety Analysis (FSAR). The meeting notice, agenda, and list of attendees are provided as Enclosures 1.
2, and 3, respectively, to this sumary.
The staff and applicant discussed the content of sections in the review materials binders collated for SPLB's review of Comanche Peak FSAR changes from Amendment 55 through 73 relating to the Comanche Peak Safety Evaluation Report, Sections 3.1, 3.5.2, 3.5.3, 3.11, 6.2, 6.5.1, 6.5.2, 9, and 10.
These binders consist of previously docketed materials (FSAR sections and applicant letters) and other publicly available materials (NUREG excerpts, Regulatory Guides, and industry standards). The tables of contents for the SPLB review meeting are provided as Enclosure 4.
Mr. Patel of TU Electric provided change pages for inclusion in the generating system review material binders. Using CPPD's most currant action list for SPLB (Enclosure 5), the staff and applicant briefly discussed the action list items referred to SPLB by CPPD for review (indictate6 by a marginal note of the "SPLB" initials next to individual bullets). The SPLB representatives also asked a number of questions on action list items not specifically referred to SPLB for review.
Two potential problems areas were highlighted during the meeting. The first area pertains to the containment analysis (SER Section 6.2.1).
TU Electric informed the staff that it needed to take credit for leak-before-break relief to reduce loads in the pressurizer and steam generator subcompartments. The staff has not granted the relief TU Electric requested for the pressurizer surge line to i
eliminate all dynamic effects of surge line rupture from the design basis under the broad-scope rule amendment of GDC 4.
The staff has deferred censideration of TU Electric's request for GDC 4 relief related to the pressurizer surge line pending evaluation of data from the Trojan Nuclear Plant's instrumented pressurizer surge line and a TU Electric bounding analysis on the stress effects of thermal stratification on the surge line. The second area pertains to reliability of the Comanche Peak station service water (SSW) system, based on design similarities with the Byron plant.* The NRC has not yet reached a "See also IE Information Notice 86-11. "Inadequate Service Water Protection Against Core Melt frequency," dated February 25, 1986, for background information on the service water system reliability issue.
8811140304 8s1107 PDR ADOCK 05000445 A
FDC l
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t Summary of Meeting on 9/29/88 conclusion on the resolution of SSW system generic concern for other affected plants, which is being addressed as Generic Technical Issue 130.
During the meeting, the staff raised several questions that require additional information from TV Electric. These actions are listed in Enclosure 6, which also includes one item for staff response back to TV Electric. The staff and applicant will discuss these items by telephone conference call (s) in the near future.
L Melinda Malloy, Project ger Comanche Peak Project Div sion Office of Special Projects
Enclosures:
1.
Meeting Notice 2.
Agenda 3.
List of Attendees 4.
Contents of SPLB Binders 5.
Action List for SPLB 6.
SPLB Information Needs cc: See next p:ge 5
l
r i
Novembee 7, 1988 Sums:y of Meeting on 9/29/88 !
t conclusion on the resolution of SSW system generic coritein for other affected plants, which is being addressed as Generic Technical Issue 130.
During the meeting, the staff raised several questions that require additional information from TV Electric. These actions are listed in Enclosure 6, which also includes one item for staff response back to TV Electric.
The staff and applicant will discuss these items by telephone conference call (s) in the near future.
(originalsignedby) f Helinda Halloy Project Manager Comanche Peak Project Division Office of Special Projects j
Enclosures:
1.
Meeting Notice 2.
Agenda j
3.
List of Attendees i
4.
Contents of SPLB Binders 5.
Action List for SPLB i
6.
SPLB Information Needs cc: See next page Distribution:
,DOCRet F1198.
3 i
[
OSP Reading CPPD Reading I
J. Partlow l
1 C. Grimes P. McKee i
i J. Lyons J. H. Wilson H. Malloy l
j W. LeFaye C-V. Li J. Craig l
A. Thadani l
J. Norberg l
L. Shao i
D. Crutch'ield i
E. Jorelan B. Grimes ACRS (10)
Nb AD:CPPD.:QS,P malloy:cm JHWilson.fh 11/4//88 11/'//88) i D 4
e W. G. Counsil Comancho Pet.k Steam Electric Station Texas Utilitie Electric Company Units 1 and 2 cc:
Jack R. Newman, Esq.
Asst. Director for Inspec. Programs New. dan & Holtzinger, P.C.
Comancho Peak Project Division Suite 1000 U.S. Nuclear Regulatory Comission 1615 L Street, N.W.
P. O. Box 1029 Washington, D.C. 20036 Granbury, Texas 76048 Robert A. Wooldridge, Esq.
Regional Administrator, Region IV Worsham, h.esythe, Sampels &
U.S. Nuclear Regulatory Commission Wooldridge 611 Ryan Plaza Drive 3uite 1000 2001 Bryan Tower. Suite 2500 Arlington, Texas 76011 Dallas. Texas 75201 Lanny A. Sinkin Mr. Honer C. Schmidt Christic Institute Director of Nuriaar Services 1324 North Capitol Street Texas Utilities Electric Company Washington, D.C.
20002 Skyway Towee 400 Porth b:lve Street, L.B. 81 Ms. Be'. lie Pirner Garde Esq.
Dallas, Texas 75201 Goverc.:.ent Acsountabilit) Proje:t Midwest Office Mr. R. W. Ackley 104 East Wisconsin Avenue Stone & Webster Appleton, Wisconsin 54911 Comanche Teak Sterm Electric Station P. O. Box 1002 David R. Pigott, Esq.
Glen Rose, Texas 76043 Orrick, Herrington & Sutcliffe 600 Montgomery Street Mr. J. L. Vota San Francisco, California 94111 Westinghouse Electric Corporation P. O. Box 355 Anthony Z. Roisman, Esq.
Pittsburgn, Pennsylvania 15230 Suite 600 1401 New York Avenue, NW Susan M. Theisen Washington, D.C. 20005 Assistant Attorney General Environments) Protection Division Robert Jablen P. O. Box 12548, Capitol Station Bonnie S. Blair Austin, Texas 78711-1548 Spiegel & McDiarnid l
1350 New York Avenue, NW Hrs. Juanita Ellis, President Washington, D.C. 20005-4798 Citizens vociation for Sound Energy 1426 Sout.
George A, Parkar, Chairman
.24 Public Utility Conunittet Dallas, 7 Senior Citizens Alliance Of Ms. Nancy irians Tarrant County, Inc.
6048 Wonder Drive CYGN/, Ene s
i
..aa 390 4rt Worth, Texas 76133 2121 N.
Walnut ( vx'
4 W. G. Counsil Comanche Peak Electric Station Texas Utilities Electric Company Units 1 and 2 cc:
Joseph F. Fulbright Tulbright & Jaworski 1301 McKinney Street Houston, Texas 77010 Roger D. Walker Manager, Nuclear Licensing Texas Utilities Electric Company Skyway Tower 400 North Olive Straat, L.B. 81 Dallas, Texas 75201 Texas Utilities Electric Company c/o Bethesda Licensing 3 Metro Center, Suite 610 8ethesda, Maryland 20814 William A. Burchette Esq.
CounselforTex-LaElectricCooperative of Texas Heron, Burchette, Ruckert & Rothwell Suite 700 1025 Thomas Jefferson Street, NW Washington, D.C.
20007 GDS ASSOCIATES, INC.
Suite 720 1850 Parkway Place Marietta, Georgia 30067-8237
ENCLOSURE 2 9/29/88 AGENDA i
FOR i P5ES UNITS 1 KNU 2 FSAR REVIEW NRC - PLANT SYSTEMS BRANCH o
INTRODUCTION:
D. R. Woodlan J. H. Wilson o
BRIEF OESCRIPTION OF SECTIONS:
M. C. Patel o
DETAIL FSAR CHANGE REQUEST:
D. R. Woodian M. C. Patel o format of Table ReviQk, Change 2equest(Bullets) o with FSAR/SER Pages o
SUMMAPY:
M. C. Patel D. R. Woodlan J. H. Wilson o
REFERENCE:
o CPSES FSAR Review Package o CPSES FSAR/SER Comparison o CPSES FSAR/SER Changes (Bullets) o NRC/TV ELECTRIC CONTACTS:
NRC:
o J.H. Wilson (301)492-3306 o
M. Malloy (301) 492-0738 TU ELECTRIC:
o D. R. Woodlan (214) 812-8225 o
M. C. Patel-(214) 812-8298 o
V. P. Cornell (214) 812-8886 s
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ENCLOSURE 3 NRC/TU ELECTRIC HETTING ON PLANT SYSTEMS BRANCH FSAR REYlEW September 29, 1988 ATTENDEES
! Lap _e_
Organization.
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ENCLOSURE 4 Tables of Contents from Plant Systems Branch Comanche Peak FSAR Review Binders j
o Flood, Mi:siles & Pipe Break (2 pages) o Environmental Qualification (3 pages) o FRT RCPB Leak Detection Containment, CSS, Control Room Habitability, and Loose Parts Monitoring (5 pages) o Auxiliary (4 pages) o Generating Systems (4 p:ges) i
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Page 1 a.
PLANT SYSTEMS BRANCH
,c, FLOOD, MISSILES & PIPE BREAK A.
FSAR SECTIONS 1.
FSAR 1.3 Table 1.3-2 all Table 1.3-1 Sht 1 of 9 2.
FSAR 3 Index 3 3-viii 3.
FSAR 3.1 all 4.
FSAR 3.4 all i
5.
FSAR 3.5 all 6.
FSAR 3.68 all 7.
Q/R (112 112-3a. 112-35, 130-5, 251-3,251-4,312-25)
B.
SER/SSER SECTIONS 1.
SER 0 Section 3.1 3-1 2.
SER 0 Section 3.4 3 3 6 3.
SER 0 Section 3.5 3 3-11 4.
SER 0 Section 3.6 3 3-14 S.
SSER fl Section 3.1 3 41 6.
SSER #1 Section 3.5 3 3-2 7.
SSER f2 Appendix E E-1 8.
SSER #3 Sections 3.4 and 3.5 3 3-2 9.
SSER f6 Section 3.6 3 3-4 i
'~
10.
SSER #12 Section 3.6 3 1 3-2 s
11.
SSER #14 Section 4.1.2.2 4 4-13 1
C.
FSAR AMENDMtNTS DESCRIPTIONS 1.
3.1 2.
3.4 3.
3.5.2 4.
3.5.3 5.
3.6 6.
3.6.1 7.
3.6.2 t
Note:
Ther0 were no FSAR changes in Amendments 55 through 72 affecting SER Sections 3.5.1.
l i
D.
LETTERS ASSOCIATED WITH FSAR CHANGES - By Topic 1.
Protection Against Effects Associated with the Postulated i
Rupture of Piping
[
a.
TXX-88118 of 1/18/88 b.
TXX-88405 of 4/25/68 c.
TXX-88425 of 5/5/88 i
I t
Pago 2 l
PLANT SYSTEMS BRANCH FLOOD, MISSILES & PIPE BREAK 1
O.
LETTERS ASSOCIATED WITH FSAR CHANGES - By Topic (contod) 2.
Determination of Rupture Locations and fjnamic Effects Associated with Postulated Ruptures of Piping a.
TXX-88078 of 1/18/88 b.
TXX-88119 of 1/18/88 c.
NRC Inspection Report 50-445/87 37 and 50-446/87-28 dated 2/8/88 (Letter and Attachments i, ii, Cover Sheet, 1 - 2, 53 - 65) d.
TXX-88332 of 4/11/88 f
e.
NRC Inspection Report 50-445/88-29 and 50-446/88-25 dated 4/14/88 (Letter and Attachment Cover Sheet, i, 11, 1 - 31) f.
TXX-88413 dated 5/27/88 g.
NRR letter dated 6/19/87 h.
NRC letter of 10/13/87 3.
Leak-Before-Break Application of GDC 4 a.
NRC letter dated 6/20/86 b.
NRC letter dated 6/8/87 E.
TECHNICAL SPECIFICATIONS p.-
1.
3/4.7.6 s
2.
3/4.7.6 Bases F.
STANDAR0 REVIEW PLAN (NUREG-0800) 1.
3.4.1 2.
3.4.2 3.
3.5.1.1 4.
3.5.1.2 5.
3.5.1.3 6.
3.5.1.4 7.
3.5.2 8.
3.5.3 9.
i.6.1
- 10. 3.6.2 G.
REGULATORY GUIDES (Selected Applicable Versions) 1.
1.46 (5/73)
H.
ANSI /ANS STANDARDS (Selected Applicable Versions) later
Page 1 FLANT SYSTEMS BRANCH Environmental Qualification A.
FSAR SECTIONS:
1.
FSAR 1A(B) 2.
FSAR 3.68 3.
FSAR 3.10N 4.
FSAR 3.108 5.
FSAR 3.11N 6.
FSAR 3.118 7.
FSAR Appendix 3A 8.
FSAR 77.5-7 9.
FSAR T9.4-2 10.
FSAR II.B.2 12.
FSAR 0/R 032.6 i
13.
FSAR 0/R 143 0.
SER/SSER SECTIONSt 1.
SER 3.10 2.
SER 3.11 3.
SSER #1 3.10 i
4.
SSER #1 3.11 S.
SSER.#6 3.6.2 6.
SSER #6 3.11 7.
SSER #12 3.10 8.
SSER #12 3.11 9.
SSER #12 T3.1, T3.2, T3.3 i
C.
FSAR AMENDMENT DESCRIPTIONS:
(Amendments SS - 72) By SER Section 1.
3.11 2.
3.11.3 0.
LETTERS ASSOCIATED WITH FSAR CHANGES BY topic 1.
Environmental Qualification Program Overview i
2.
Environmental Qualification Audit (s)
- a. Txx-3631 dated 2/24/83
- b. TXX-3630 dated 2/23/83 t
- c. TXX-3615 dated 1/24/83
- d. NRR Letter dated 12/14/82 y
- e. NRR Letter dated 10/14/82 l
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,.., -. - - - - - _., - -, -. ~ -, _. _,.. - -,,,.
Page 2 PLANT SYSTEMS BRANCH Environmental Qualification D.
LETTERS ASSOCIATED WITH FSAR CHANGES BY TOPIC (cont'd) 3.
Environmental Qualification (General)
- a. Txx-3997 dated 6/28/83
- b. TXX-3683 dated 6/7/83
- c. Txx-3662 dated 5/5/83 4.
Juttification(s) for Interim Operation
- a. TXX-4196 dated 1/15/85
- b. TxX-4304 dated 9/20/84
- c. TXX-4301 dated 9/19/84
- d. TXX-4208 dated 6/29/84
- e. NRR Letter dated 12/14/84 (Closure of Confirmatory issue 18) i 5.
Environmental Qualification of Safety Related Mechanical Equipment in Potentially Harsh Environment
- a. TXX-4420 dated 2/15/85
- b. TXX-4392 dated 1/10/85
- c. TXX-4233 dated 7/20/84
- d. NRR Letter dated 5/29/84
[
- e. TXX-4105 dated 2/7/84
- f. NRR Letter dated 12/10/83
- 9. TXX-3682 dated 6/7/83
- h. Txx-3652 dated 3/30/83 6.
BlW Cable t
- a. TXX-4280 dated 8/23/84 l
1
- b. TXX-4254 dated 8/10/84 L
- c. NRR Letter dated 7/19/84 i
7.
Mild Environment E
)
TXX-6885 dated 10/27/87 i
8.
HELB/MSLB i
- a. TXX-88043 dated 1/7/88 f
- b. TXX-6360 dated 3/27/87 i
- c. TXX-4413 dated 2/14/85 t
- d. NRR Letter dated 12/21/84
- e. Txx-4293 dated 8/30/84
- f. TXX-4092 dated 1/5/84 L
- g. TXX-4048 dated 9/13/83 j
(Note: TXX 88043, TXX-6360 and TxX-4293 are associated i
j with SDAR 84-12.
Remaining Interim responses l
which indicated a continuing evaluation only, I
were r,St included.)
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8 O
P.'ne 3 4
PLANT SYSTEMS BRANCH Environmental Qualification E.
TECHNICAL SPECIFICATIONS 3/4.7.11 F.
STANDAR0 REVIEW PLAN (NUREG-0800) 1.
3.10 2.
3.11 3.
3.6.1 Appendix B Branch Technical Position ASB 3-1 4.
3.6.1 Appendix C Branch Technical Position ASB 3-1 G.
REGULATORf GUIDES 1.
1.30 8/725 2.
1.40 3/73 3.
1.73 1/74 4
4.
1.75 1/75 5.
1.89 11/74 6.
1.97 12/80 i
7.
1.100 8/77 8.
1.131 8/77 H.
IEEE STANDARDS 1.
317 - 1976 2.
323 - 1974 3.
323a -1975 4.
334 - 1974 5.
344 - 1975 6.
382 - 1972 7.
383 - 1974 1.
OTHER APPLICA8LE DOCUMENTS 1.
NUREG-0588 2.
Page 1 PLANT SYSTEMS BRANCH (PRT, RCPB LEAK DET, CNTHT, CSS, and CR HAB AND LOOSE PARTS MONITORING)
A.
FSAR SECTIONS 1.
FSAR 1A N) R.G. 1.1 1A 1A(N)-3 2.
FSAR 1A N) R.G. 1.7 1A
-6 3.
FSAR 1A R.G. 1.11 1A
-7 4.
FSAR 1A R.G. 1.22 1A
-13 5.
FSAR 1A R.G. 1.26 1A
-14 6.
FSAR 1A R.G. 1.29 1A 1A(N)-16 7.
FSAR 1A R.G. 1.1 1A
-1 8.
FSAR 1A R.G. 1.4 1A
-2 9.
FSAR 1A R.G. 1.7 1A
-3 10.
FSAR 1A' R.G. 1.11 1A
-5 11.
FSAR 1A R.G. 1.26 1A
-11 12.
FSAR 14 R.G. 1.29 1A
-12 13.
FSAR 'A R.G. 1.45 1A 1 A(B)-19 14.
FSA? *.A R.G. 1.46 1A
-19 15.
FSAR 1A R.G. 1.52 1A lA(B)-23 16.
FSAR 1A R.G. 1.78 1A
-47 17.
FSAR 1A R.G. 1.82 1A
-49 18.
FSAR 1A R.G. 1.95 1A
-55 19.
FSAR 1A R.G. 1.133 1A
-71 20.
FSAR 4.4 4.4 4.4-59 21.
FSAR 5.2.5 5.2 5.2-56 22.
FSAR 5.4.4 5.4 5.4-50 23.
FSAR Fig. 5.d-5 24.
FSAR 5.4.5 5.4-50 25.
FSAR 5.4.11 5.4 5.4-80 26.
FSAR Table 5.4-12 27.
FSAR Table 5.4-13 28.
FSAR 6.g. 5.1-1 FSAR Fi Sht 2 29.
2.1 6.2 6.2-62 30.
FSAR Tables 6.2.1 6.2.1-93 31.
FSAR Fig. 6.2.1 6.2.1-59 32.
FSAR 6.2.2 6.2 6.2-84 33.
FSAR Table 6.2.2 6.2.2-5 34.
FSAR Fig. 6.2.2 6.2.2-5 35.
FSAR 6.2.3 - 6.2.4 6.P 6.2-103 36.
FSAR Table 6.2.4 6.2.4-6 37.
FSAR Fig. 6.2.4-1 Sht 1 - 10 t
38.
FSAR 6.2.5.
6.2-104 - 6.2 127 39.
FSAR Table 6.2.5 6.2.5.5 40.
FSAR Fig. 6.2.5 6.2.5.3 41.
FSAR 6.2.5A 6.2-127 - 6.2-138 42.
Ff'.R Table 6.2.5A 6.2.5A-6 43.
FSAR Fig. 6.2.5A 6.2.SA-9 44.
FSAR 6.2.6 6.2-138 - 6.2-147 45.
FSAR Fig. 6.2.6-l' l
46.
FSAR 6.4 6.4 6.4-16 i
Page 2 PLANT SYSTEMS BRANCH (FRT, RCP8 LEAK DET, CNTMT, CSS, ard CR HAB AND LOOSE PARTS MONITORING)
A.
FSAR 3ECTIONS (cont'd)
- 47. FSAR Table 6.4 6.4-4
- 48. FSAR Fig. 6.4 1 - C.4-3
- 49. FSAR 6.5 & 6.5.1 6.5 6.5 6
- 50. FSAR 6.5.2 - 6.5.4 6.5 6.5-34 51.
FSAR Table 6.5-1 6.5-7 52.
FSAR Fig. 6.5 6.5-4 53.
FSAR !!.E.4.1 II.E-26
- 54. FSAR !!.E.4.2 II.E II.E-29
- 55. FSAR 111.0.1.1 111.0 !!I.0-5 56.
FSAR !!!.0.3.3
!!I 0 111.0 8 57.
FSAR 111.0.3.4 111.0 !!!.0.11
- 56. FSAR 0/R 022.3 022 022-22 59.
FSAR 0/R 022.5 022-24 60.
FSAR Q/R 022.10 022-35 r
61.
FSAR 0/R 022.20 022 022-52
- 62. FSAR 0/R 022.22 022-55 4
- 63. FSAR 0/R 032.85 032 032-98 64.
FSAR Q/R 220 220-1 220-2 r
65.
FSAR 0/R 312.4 312-4 66.
FSAR Q/R 312.8 312-9 67.
FSAR 0/R 312.10 312-11 68.
FSAR 0/R 312.27 312-30 69.
FSAR Q/R 4?3.12 423 423-31a l
B.
SER/SSER SECTIONS 1.
SER 5.2.5 5 5-9 2.
SER 5.4.4 5 5-21 3.
SER 5.4.5 5-21 4.
SER 6.2.1 6 6-8 5.
SER 6.2.2 6 6-9 6.
SER 6.2.3 6 6 12 7.
SSER #6 6.2.3 6 6-2 i
8.
SER 6.2.4 6 6-13 9.
SER 6.2.5 6-13
- 10. SSER #6 6.2.5 6 6-3
- 11. SSER #12 6.2.5 6 6-2
- 12. SER 6.4 6 6-20 i
- 13. SER 6.5-6.5.1 6 6-21
- 14. SER 6.5.2 6 6-23
- 15. SSER f3 6.5.2 6 6-2
- 16. SER II.E.4.1 22 22 52
- 17. SER ll.E.4.2 22 22 55 l
- 18. SSER #12 !!.E.4.2 22 2-18
- 19. SER !!!.D.1.1 22 22-89
- 20. SSER #4 111.0.1.1 22-3 t
21.
SER 1:1.0.3.3 22 22-91 22.
SSER #6 111.0.3.3 22 16
- 23. SER !!!.0.3.4 22 22-94 l
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Page 3 PLANT SYSTEMS BRANCH (PRT, RCPB LEAK DET, CNTMT, CSS, and CR HAB AND LOO 5E PARTS HONITORING)
C.
FSAR AMENDMENT DESCRIPTIONS (Amendments 55 through 72) - by related SER Section 1.
4.4 2.
5.2.5 3.
6.2 I
4, 6.2.1*
5.
6.2.2 6.
6.2.3 7.
6.2.4 8.
6.2.5 9.
6.4 10, 6.5.1 11, 6.5.2 12.
111.D.3.3 I
- Note:
There were no FSAR changes in Amendments 55 through 72 affecting Sections 5.4.4, 5.4.5, 6.2.1,
!!!.E.4.1, ll.E.4.2, !!!.D.1.1 and 111.0.3.4.
D.
LETTERS ASSOCIATED WITH FSAR CHANGES 1.
[
a.
TXX-4009 of 7/19/83 b.
TXX-4386 of 12/21/84 c.
TXX-4419 of 2/12/35 d.
TXX-4618 of 1/20/86 e.
Proposed Rule Vol. 53 No. 39 of 2/29/88 l
2.
M51V Bypass Valves f
a.
TXX-4479 of 5/1//85 b
TXX-4510 of 7/10/85 c.
TXX-6126 of 12/8/86 l
Header Isolation Valves Containment Spray /11/85 3.
a.
TXX-4437 of 3 b.
TXX-6435 of 5/13/87 c.
T.".X-88441 of 5/20/88 4.
Containment Piping Penetrations a.
TXX-6955 of 12/1/87 b.
TXX-88110 of 1/20/88 5.
Fluid Transient in the Steam Supply Line for the Turbine Driven Auxiliary feedwater Pump a.
TXX-88520 of 5/29/88 I
i f
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Page 4 PLANT SYSTEMS BRANCH (PRT, RCPB LEAK OET, CNTMT, CSS, and CR HAB AND LOOSE PARTS MONITORING) f E.
TECHNICAL $PECIFICATIONS 1.
1.0 2.
3/4.3.2 t
3.
3/4.s.3.7 a
4.
3/4.3.3.9 5.
3/4.4.6 r
6.
3/4.5.2 7.
3/4.6.1 8.
3/4.6.2 i
9.
3/4.6.3
- 10. 3/4.6.4 l
- 11. 3/4.7.7
- 12. 3/4.7.8 13.
3/4.9.9
- 14. 5.2
- 15. 6.5 i
- 16. 6.8 l
F.
STANDARD REVIEW PLAN (NUREG-0800) i 1.
4.4 2.
5.2.5 3.
5.4 4.
5.4.11 i
5.
6.2.1 6.
6.2.1.1.A i
7.
6.2.1.2 l
8.
6.2.1.3 i
9.
6.2.1.4 l
10.
6.2.1.5 4 CSB-6-1. Table 1, Fig. 1 e 2 i
4 i
11, 6.2.2
[
12.
6.2.4 & CSS-6-4
[
- 13. 6.2.5 & App. A 14.
6.2.6 t
- 15. 6.4 & App. A. Table 6.4-1 16, 6.5.1 t
j 17.
(.5.2 & Fig,. 6.5.2-1 4
i
o o
Pago 5 PLANT SYSTEMS BRANCH (PRT, RCPB LEAK DET, CNTHT, CSS, and CR MAB AND LOOSE PARTS HONITORING)
G.
REGULATORY GUIDES 1.
1.1 (11/2/70) 2.
1.4, Rev. 2 (6/74) 3.
1.7, Rev. 1 (9/76) & Rev. 2 (11/78) 4.
1.11 (3/10/71) 5.
1.22 (2/17/72)
..5.
1.26, Rev. 3 (2/76) 7.
1.29, Rev. 2 (2/76) 8, 1.45 (5/73) 9.
1.46 (5/73) 10.
1.52, Rev. 1 (7/76) & Rev. 2 (3/78) i, 11.
1.78 (6/74) 12.
1,82(6/74) 13.
1.133 (9/77) (1/77) 1.95, Rev. 1 14.
H.
IEEE STANDARDS 1.
279 - 1971
Page 1 PLANT SYSTEMS BRANLI (Auxiliary)
A.
FSAR SECTIONS 1.
FSAR Sec. 9.1 2.
FSAR Sec. 9.2 3.
FSAo Sec. 9.3 l1 4.
FSAR Sec. 9.4 (all 5.
FSAR Sec. 9.5 4 - 9.5.8 (all 6.
FSAR Sec. lA R.G. 1.13 1A 6
7.
FSAR Sec. lA R.G. 1.104 1A 58 8.
FSAR Sec. 1A R.G. 1.27 1A
-11 9.
FSAR Sec. lA R.G. 1.52 1A 21 - 1A(B)-23 1
- 10. FSAR Sec. lA R.G. 1.140 1A 74 & 75 11.
FSAR 0/R 400.3 400 400-5 l1
- 12. FSAR Tables 2.3-7. 5.2-5, 6.4 4, 6.5-1 13.
FSAR Figures 1.2-23, 10.4-11 8.
SER/SSER SECTIONS 1.
SLR Sec. 9.1 2.
SER Sec. 9.2 3.
SER Sec. 9.3 4
SER Sec. 9.4 (all 5.
SSER #1, Sec. 9.1.4 9-1 i
(
6.
SSER 86, Sec. 9.1.4 9 1 & 9-2 7.
SSEP. #C. Sec. 9.3.3 9-2 8.
SSER #12. Sec. 9.1.5 9-1 9.
SSER #3, Sec. 9.4.6 f1
- 10. SSER #4, Sec. 9.4.4 9-1 & 9-2
- 11. SSER 86 Sec. 9.5.9 9 9-13 C.
FSAR AMENDMENT DESCRIPTIONS 1.
FSAR Section 9.1:
Lendments 57, 60, 66, 68, 71 l1 2.
FSAA Section 9.2:
Amendments 55,56,57,60,66,67,68,69 3.
FSAR Section 9.3:
Amendments 56, 66, 67, 68, 69, 72 l1 4
4.
FSAR Section 9.4:
Amendments 56, 59, 6C. 66, 68. 70. 71. 72 l1 5.
FSAR Sections 9.4.5 thru 9.4.8:
Amendments 59, 66, 68, 70 l1 Revision 1
o Page 2 PLANT SYSTEMS BRANCH (Auxiliary)
O.
LETTERS 1.
NRR Letters:
piRA~63&E 12/5/85 a
b NRR-6086, 11/27/84
))NRR6015,9/21/84 c
d NRR 5066, 7/26/84
)INRR5000,5/17/84 e,f NRR 3095, 2/9/84
)OSP74,10/19/87
)OSP80,10/29/87 g
h J))OSP92,11/6/87 i
0$P-88, 11/10/87 J
?.. TV Electric letterst a TXX-88399, 4/22/88 b TXX-6716, 9/11/88 c TXX-6323, 3/9/87 d TXX-6148, 12/15/86 e TXX 4718, 2/23/86 1
1f TXX 4643 12/16/85 1
))lTXX-4395,1/16/85 TXX-4545, 9/4/85 g
hj TXX-4277, 8/21/86
)TXX-4226,7/12/86 l1 k)TXX-88699,9/23/88 IJ l1 E.
SELECTED SDAR'S (10CFR50.55(e) REPORTS:
1.
SDAR CP-81-003, TXX-3349 of 6/23/81 TXX-3307 of 4/24/81 2.
SDAR CP 83e007, TXX-3677 of 5/31/83 3.
SDAR CP-83 018 TXX-4054 of 9/26/83 TXX-2350 of 4/9/85 4.
SDAR CP-83-022, TXX-4098 of 1/18/84 5.
SDAR CP-84-027. TXX-4409 of 3/6/85 TXX-6435 of 5/13/87 6.
SDAR CP 86 007 TXX-88476 of 6/22/88 TXX-4762 of 4/11/86 7.
SDAR CP-86-011 TXX 6960 of 11/17/87 TXX-4871 of 6/23/86 8.
SDAR CP-86-018, TXX-88262 of 2/26/88 TXX-4A20 of 5/?l/i%
9.
SOAR CP-86-022, TXX-fta440 of 6/It/m I AA bS51 ol //tt/tt/
10.
SDAR Cp 87-020. TXX 88107 ut 1/18/88 l1 11.
50AR CP-87-116. TXX.88547 of 6/30/88 TXX-88343 of 3/30/88 TXX-88004 of 1/13/88 12.
SDAR CP-87-130. TXX-88459 of 5/13/88 TXX-88034 of 1/6/88
'XX-88159 of 2/4/88
SDAR CP-88-001, TXX-88114 of 1/18/88 Revision 1
Page 3 PLANT SYSTEMS BRANCH (Auxiliary)
F.
TECHNICAL SPECIFICATIONS 1.
FSAR Section 9.11 l
T/5 Sections 5.6, 3/4.9.1. 3/4.9.2, 3/4.9.6, 3/4.9.7, 3/4.9.10 2.
FSAR Section 9.2:
T/5 Sections 3/4.3.2, 3/4.7.1.3, 3/4.7.3, 3/4.7.4, 3/4.7.5 3.
FSAR Section 9.3:
T/5 Sections 3/4.1.1, 3/4.1.2, 3/4.9.1 4.
FSAR Section 9.4:
T/5 Sections 3/4.7.7. 3/4.7.8. 3/4.7.11 G.
STANDARD REVIEW PLAN (NUREG-0800) 1.
SRP Sec. 9.1.1 2.
SRP Sec. 9.1.2 3.
SRP Sec. 9.1.3 4.
SRP Sec. 9.1.4
(
S.
SRP Sec. 9.1.5 6.
8TP AS8 9-1 7.
SRP Sec. 9.2.1, Rev. 4 and 3 8.
SRP Sec. 9.2.2, Rev. 3 and 2 9.
SRT Sec. 9.7.3 10.
SRP Sec. 9 2.4 11.
SRP Sec. 0.2.5 12.
BTP ASB 9-2
- 13. SRP Sec. 9.2.6
- 14. SRP Sec. 9.3.1
- 15. SRP Sec. 9.3.2 16.
SRP Sec. 9.3.3 17.
SRP Sec. 9.3.4 1
18.
SRP Sec. 9.4.1
- 19. SRP Sec. 9.4.2 l
- 20. SRP Sec. 9.4.3 21.
SRP Sec. 9.4.4
- 22. SRP Sec. 9.4.5
- 23. SRP Sec. 9.5.4 thru 9.5.8 H.
REGULATORY GUIDES 1.
NRC R.G.1.13 Rev.1,12/ 7')
i 2.
NRC R.G. 1.27, Rev. 1, 3/74 3.
NRC R.G. 1.27. Rev. 2. 1/76 4.
NRC R.G. 1.104, Rev. 1, 10/78 5.
NRC R.G. 1.52, Rev. 1, 7/76 6.
NRC R.G. 1.52, Rev. 2, 3/78 7.
NRC R.G. 1.140, 3/78 8.
NRC R.G. 8.8, Rev. 2
.-,--www--
e
Page 4 PLANT SYSTEk3 BRANCH (Auxiliary) 1.
MISC. STANDARDS 1.
NUREG 0554 2.
NUREG-0612, 6/83 3.
ANSI N-509, 1980 4.
ANS! N 510, 1980 4
7
Page 1 s
PLANT SYSTEMS BRANCH GENERATING SYSTEMS I.
FSAR SECTIONS:
1.
FSAR Section 10.1 ALL 2.
FSAR Section 10.2 ALL 3.
FSAR Section 10.3 ALL 4.
FSAR Sectian 10.4 ALL 5.
FSAR Section !!.E.1.1 II.E-1 thru ll.E-16 6.
FSAR Section II.E.1.2 II.E 16 thru ll.E-23 7.
FSAR Section II.K.2.19 II.K-6 thru ll.K-7 8.
FSAR Q&R 040-137 l
l SER/SSER SECTIONS:
1 1.
SER Section 10.1 2.
SER Section 10.2 3.
SER Section 10.3 4.
SER Section 10.4 5.
SER Section 22.2; Sub Section II.E.1.1 22 38 thru 22-46 6.
SER Section 22.2; Sub Section !!.E.1.2 22 46 thru 22-49 7.
SER Section 22.2; Sub Section II.K.2.19 22-72 8.
SSER #4; Sub Section 10.4.5 10-1 and 10 2 9.
SSER #4; Sub Section 10.4.7 10 2
- 10. SSER #12; Sub Secticn 10.4.9 10 1
- 11. SSER #12; Sub Section 10.3.1 10-1
- 12. SSER #6; Sub Section 10.2.2 10-1 thru 10 9 III.
FSAR AMENOMENT DESCRIPTIONS:
(Amendments 55 thru 72) - by related SER Section 1.
10.1 Amend 59 2.
10.2 Amend 55, 65, 68 3.
10.3 Amend 55, 56, 65, 66, 67, 69, 70 4.
10.4 Amend 55, 57, 59, 60, 65, 66, 67, 68, 69, 71, 72 o
W
Page 2 PLANT SYSTEMS BRANCH GENERATING SYSTEMS IV. LETTERS:
l A.
TXX letters to NRC:
1 1.
Section 10.2.2 a).
TXX-4297, dated 9/11/84 2.
Section 10.3 a).
TXX 4478, dated $/21/85 b).
TXX-6398, dated 4/15/87 3.
Section 10.4.5 a). TXX-4643 4.
Section 10.4.9 a.
TXX-88456, dated 5/17/88 b.
TXX-88556, dated 7/8/88 e.
TXX-6074, dated 10/28/80 d.
TXX-4301, dated 9/19/84 B.
NRC letter tr, TU Electric:
1.
Sectior. 10.2 a). SRR-6001, dated 9/6/84 b). NRR-5056, dated 2/28/24 2.
Section 10.3 a.
NRR-6430, dated 2/27/86 b.
NRR-6232, dated 7/5/85 c.
NRR-5039, dated 6/19/84 3.
Section 10.4.5 a). MR letter, dated 12/10/85(notattached) 4.
Section 10.4.9 a.
MR 6883, dated 5/5/88 b.
MR-6843, dated 2/17/88 c.
MR Ietter, dated 8/5/85 (notattached) 5.
Section 10.4.16 a). NRR-6047, dated 10/25/84
Page 3 PLANT SYSTEMS BRANCH GENERATING SYSTEMS V.
SELECTEDSDAR'S(10CFR50.55(e) Reports):
1.
FSAR Section 10.3:
a). SDAR: CP-87 019 1
2.
FSAR Section 10.4.7 a).
SDAR: CP-87 028 i
3.
FSAR Section 10.4.9 a.
SDAR: CP-85 012 b.
SDAR: CP-87-050 e.
SDAR: CP 88 013 VI. TECHNICAL SPECIFICATIONS:
1.
10.1 a.
3/4.7.1, 7.2 2.
10.2 a.
3/4.3.2, 6.8 3.
10.3 a.
3/4.4.10, 7.1.1, 7.1.5, 7.2, 6.3, 6.8 4.
10.4.7 a.
3/4.7.1.2, 3.2 l
5.
10.4.9 a.
3/4.7.1.2, 3.2 6.
10.4.16 a.
6.6. 3/4.7.1.4 V11.
STANDARD REVIEW PLAN (NUREG-0800)'
1.
10.2, 10.2.3 2.
10.2, 10.3.6 3.
10.4.1 4.
10.4.2 5.
10.4.3
4 e
Page 4 PLANT SYSTEMS BRANCH GENERATING SYSTEMS 6.
10.4.4 7.
10.4.5 8.
10.4.6 9.
10.4.7
- 10. 10.4.8
- 11. 10.4.9
- 12. BTP AS8 10 1 Vill. REGULATORY GUIDES (SELECTED AITLICASLE VERSIONS) none
!X.
INDUSTRY STANDARDS (SELECTED APPLICABLE VERSIONS) none l
l e
4 4
J 1
1
__r.
gum-
- --'7
O 9.t v ee o
ENCL.05URE 5 "la de edH.
Action List for $Pt.8 he (TAC No. R00410)
, r.3 6 b dnem hr L 4. &m d o
i SER Sect %ft aise /
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- g;sttee 8' e litenails ee*4'at eg e ggi,et le e ; egge (pesegge enter seene t 8' ens e 6vse, neseaw :e:Ht ion
,,,,a 1, C y
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e 3;)e I e I 'efilee $ leet 1846,4 lett 4 I"I" i e e 4+en.r uet 8e460' f ee
- g e e 1,,line treets testee
) 4 ) Leele e4'st seesty
- g, g g,, ;g q,, g v t N e 2.1 (3staiseeet f.*tt neesk *et;1 il e 3 Cpeest4Le de Geoestes 111tN e ; ; lptatseest out lese,441,uen 1% 4 9 healllPe Icehte# Ifuse e ! I tests.*wt !ssistir listet retell s listilits tienest
- a o
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e 14 (Hoottille 444 fe8t'el If gtso t[ [ g g gegigegg (segging g essegestgang
- ! 1 (Ptetsaeet tesagte fettgeg esegese
'l ( 4 2 teategnesel llenstsee lesee84Billtf i i ete f ee6 llosege
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!C:eeestet ;Mitsg ester 1,ttHp 1 e t Blpt leu p ': c'etetttaa ateiett 8ette! stet teilestisr..!teuen e
e se,e #4te* lettee e ; ; :nievettaes we texter s
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! e ! eate te,el ' flee 41 totip e'uese et r
e t e t :st+en om 6 tee opttlet.to fittes i e e s4tte 44% ItttM l e ils's i e 7 f ut seeslig teils.st eetilettes lettee I ' ' ' """I * "
- N I * *" ' I'" " M 8' " ' b ! *' '
e e, s.ed.v, 4.daty es teseatte eres seet:14tten
.)ee u se:
- e* 8 e s..* *i g
e 1 i tittee :nc*ist.e es (.6ut.ee
- I'."f e. :
t 4 e ta'epe'st I,s.tal et tiaties tvuee u.
este 8 ten.'s. nee M
'***1""' W"W h""
e e i e.neite' eses lonelig eestnisties Inteet 3"""""'
' " # ' I'" "
- tut e4 l's.. eat e s;st:lita. *ettss ty
- I e taf ett Cntilet te4er lettet t.
a letteet 5 e e 8 erg eas tittel 151Pe f eel hl !! 'au el
- et'e' i,Stu
- ) 4 ) ggg of *;g!stl 4tt;te*t j
e ) ) liesel le*e'ete'..f el;*4 44te' !st!?e d a g s,ei. pen q g ;,te.g ea e lee teat, ant
- i*e !!v t;'t f et
- H e a :3*t 3; e :o.el.14tn ote s
a > ' t oe. p.;, '...e, t y i.e..t.
4t.*4 1 tettes i i, levie:, Onei t pe.: eve,.t:p a :steo er
- % e let*teate title; tagies celatilits le*sett 1sttee i 5.eur, tew ist ina
!t
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- . osus 'atut.ee f..in e
e.te i:t.e i.n.
.u o
.e a r t n,q s.e n ea ;..et a....n e e Review respons1bilities are irdiC3ted by 3 ranch initidl$ in the margin, Undesignated items will be reviewed by CFF0 indeendently or with censultati:n with the Cognizant review branch.
SECTION 3 - CESIGN CRITERIA FOR STRUCTURCS, SYSTEMS AND CCMPONENis The requirement to use N 5 data report forms nas tven relaaeo :s 3.1 using ASME Data Report Furms generally.
The SER neous to be revised to reflect new desigs tasts =nten IM
/IM T"O incorporates leak-cefore-break netnocology, TheuninterruptiblePowerSupply(UPS)AreaAirConditioning 3.2.1 <
System has been accea to the Seismte anc Q-itsts 'n tne FSAn (includes enanges to Table 3.2 3, Sheet 5 and Table 17A-ll.
The FSAR has removed the riescripticn of fire prote: tion systems separation relation to seismic Category [ equiprent.
The FSAR r reflects treat seismic Category I cranes and noists will
~
maintain envir structural integrity during and af ter the $$E witn lifted load, except for the polar crane wnich is qualified for G6E with lifted load and SSE without lifted load.
The FSAR now exerpts Class 5 air-filled copper tubing up to L2
- 4" in ciameter from consideration as to impact on Setsmic !
systems (lighter and has less potential for damage than 2" steel pipe which was cas4s for analysisi, The FSAR nnw liteludes 'NC-3200" qualit) *tandards requirements for Safety Class 2 pressure vessels, as cis quality standard.
was used for the Safety injection Accumulator Tanks.
The FSAR now provides for use of Sater optional Code revisions (including code cases) in accordance with the requirements of 10 CFR 50.55a.
The SER incor.*ectly states that all Class 2 components in fluid systems teportant to safety are constructed i't accorcance with Table 3.2-1 lists steel lined Section !!! of the ASME Code.
concr6te storage tanks that are Safety Class 2 as be' constructed to AC1 318, vs. ASME-!!!.
Table 17A-1 has changed the Itne entries for safety class, seismic category or applicable code or standard, Mr a numer of components.
The dusign wind force on a rectar. gular struc'ure has changed from j
3.3.1
- 7Q to 80, The gust factor for Category 1 tanks nas changed from t.1" to "1.5" i
1 per ASCE Paper 3269.
The FSAR has had minor changes to modify description of toiSado Jam.
3.3.2
- pers and blowout panels ano doors.
There has been a design change for all seismic Category 1 structwres (now designed to atthstano a 360 mph t:enaco).
The SER neecs to raflect enat an exception is taken to RG 1.76 (Section 14 s) page 1A(6)-49) in that 1 psi pressure drco per sec:cd ESGB l
is used for cesign ratner tnan 2 pst,sec.
A numcer of changes nave teen. race as a result of torna u venting cons t oe rat 1cr.s.
l r
. Section 3 (continued)
~
$taff.needs to revtew compliance with tornaco-generated missile
~
f d tB 3.5.2
- criteria of Spectrum 11. Regten ! (used to te 1975 missile scectrum A).
Ine F5AR nas added Class 1E appurtenances to the Fd Control Valves anc
'; sL B their associated bypass valves to list of safet).relatec cce;onents not cont:ined witnin a concrete structure (response to Q312.22).
List of Class 1E apourterances on p. 3.5-22 are not protecteo from
!;L3 tornado missiles. Credit is taken only for the valves for f.L8s ard MSL8s inside containrent. These oice ruptures are not postulatec to occur simultaneously with a tornado.
--eptt gS6 83.5.3
- The FSAR has defined the ductility criteria for steel columns isttn a slenderness ratio greater than 20 in order to deteretne the overall resper.se of structural barriers to missile impact The SER needs to reflect that the applicant has submitte.. ~nformaticn mggg confirming design acequacy of steel and reinforced concrete mtssile barriers over the diesti fuel storage tanks (as stated on p. 3-10 of tne SER).
The FSAR has been revised for Reactor Coolant Loop piping to reflect 3.6.1
- leak before break r4thodology.
The SER needs to reflect that some items of equipment required,for shutdown have been relocated as a result of the flooding evaluation associated wito pipe creaks.
Staff needs to review the FSAR reference to the ASPE Code for cetermination of minisium ultimate uniform stress for pipe whip restraints.
Staff detos to review and approve TV Electric's request to apply EMT3
'eak brear methodology to specific branen lines (TXX-88382)
The PIPERUP C1de is corrected to be radeled using a bilinear stiffness curve insteao of the previously stated trilinear stiffness code.
Table 3.f ' ' has been revisto to require high energy consideration durin; e * +..cy condition only for certain lines.
3.6 J '
Location of nirge ano directicn of pipe r4verent due to a pipe bresk has been reviewed by staff and documented in IR 50-445/87-37 and 50 446/87-28.
The FSAR has been revtsed for Reactor Coolant Loop piping to reflect leak before break methodology.
i The FSAR now states tnat the RCS hELB's were costulateo per AStiE Code 1977 Edition througn Sursner of 1979 (prev 1cusly used 1974 Editicn through Winter 1974).
Staff needs to vertfy the acceptability of rethodology for encesing inter-ediate breat lccations.
The SER neeos to reflect snat GL 67 11 and hRC letter of *,C/13,57 nave upproved elimination of Aroitrary intermediate breaks.
ne FSAR has redefined tne break exclusion area inside centainment.
The FSAR has replaced RELAP-3 witn RELAP-5 and PLOTR witn CALPLOTF CJmGutar cooes.
Computer coces 5hPLAST 2267 and ACASLS-NO nase been addec to supplement P:?E hP.
o
. Sec'eton 3 (continued)
Staff.needs to review conspliance with '.ornaco-generated missile SPL5 3.5.2
- criteria of Spectrum 11 Region ! (used to ce 1975 missile stectr.m A).
The FSAR nas added Class 1E appurtenances to the Fd Contrei Valves cr.c SPLS
- neir a sociated bypass valves to list of safety relatec cce;onents not contained witnin a concrete structure (response to Q312.22).
List of Class 1E accurterances on p. 3.5-22 are not protecteo frem SFLS tornado missiles. Credit is taken only fc- :ne valves for f.Las are MSLBs inside contatuent. These pipe ruptures are not postulatec to occur simultaneously witn a tornado.
The FSAR has defined the ductility criteria for steel columns witn id f568).5.3
- a slenderness ratio greater than 20 in order to cetermine the overs 11 respchse of structural Larriers to missile impact.
The SER needs to reflect tnat the applicant has sutettted inforeation
,ggLg.g g g confirming cesignsacequacy of steel and reinforced concrete missile Darriers over tne diesel fuel storage tanks (as ssated on p. 3-10 of the SER).
N The FSAR has been reytSed for Reactor Coolant Loop piping to reflect 3.6.1
- leak-before-break eetnodology.
The SER needs to reflect that some items of equipment required.for shutdown have been relocated as a result of the flooding evaluation associated with pipe creaks.
Staff needs to review the FSAR reference to the ASME Code for cetermination of minimum ultimate uniform stress for pipe wntp restraints.
Staf f nevos to review and approve TU Electric's request to apply EMTS leak thrifaTPetaodology to specific branen lines (711-88382).
The P!PERUP Code' % orrected to be.rodeled using a btitrear stiffness curve (qstead of the pr* iously stated trilinear stiffr~ is code.
Table 3.6 6-1 has been re q to require high energy consideratie's N5'O
- it h
.cJ, e ce'rtain lines, during hm M;::: */'m4 fem m'
Location of' hinge and directicn of pipe =ovecent due to a pipe break 3.6.2 '
nas been rev) wed by staff and docueented in IR 50 445/87-37 ana 50 446/87 28.
Tne FSAR has b en revised for Reactor Coolant loop piping to reflect leak before-bre'ak methodology.
The F5AR now stites that the RC5 HELI:l's were postulateo per a5 fit Code 1977 Edittoh throuyn Sueur.er of 1979 (preytcusly usea 1974 Editten through Winter 974).
Staff needs :
trify the acceptability of methcdology for encesing tatar te; creat locations.
The SER neecs to reflect tnat GL 6711 and MC letter of ;C/13/57 nave approved elimination of areitrary intermediate breats.
Tne FSAR has redefined tne breat exclusion area instav ccntatnrent.
The F5AR has replaced RELAP 3 witn RELAP 5 ar.d PLOTR witn C,V LOff l
computer codes.
Computer ccces inPLAST 2257 and ACABLS-ND nave teen accec to swpplerent 7:7E hP.
i l
3-Section 3 (continued) r 3.6.2 (continued)
A nuncer of FSAR figures have oeen revised to reflect newest creat locations based on stress analysis.
TU Electric has pN ideo for low concentration of essential caole in svoerpipe area to satisfy the cauttonary note wnicn nas replaceo tne SRP requirement to analy2e tne Jet impingeeent ef fects un a one square foot arbitrary breat.
The FSAR has reviewed the retnocology used to determine get impinge ent, DES loads (now employ metnoco!ogy in AP.S!/aNS 58.2. P.av. 7,1367).
3.68 960 nas been acced to relate stagnation suecooling at Figure EMEB the break plane to stagnatten condittens in the vessel supplying tre jet flow, accounting for trreverstele losses in tne letecwn line, pgg Figure 3.68 970 has teen added to calculate the Asystotic Area Ratto and which may be used in place of an equation.
The FSAR has been revised to expand the cefinition of break exclusion I
DEg area bouncary and includes a description of the method for cetermining the jet cone shape for Category Il jets.
TV Electric has taken an excep' ion to RG 1.61 by using Code Case N 411 3.7.1
- damping values for piping systems using the response spectrum method (also, stress problems will be identifind).
The text and figures for horizontal and vertical response spectra and artificial time history have been revised to reflect that five damping values have been used for one earthquake, rather than five separate ea'.thouakes, as previously irplied.
The FSAR has changed the description of how the artificial time i
i histories for the seismic analysts were validated.
The staft needs to review seismic design for service water intake 3.7.2 *
(new structural model including technicues used to generate stif f-ness properties and foundattun response), including Tables.
The staff needs to revtew the use of tecnniques to generate stiffness properties for seismic Category 1 tanks (FSAR new uses standard l
structural techniques, i.e., hand calculation, not finite element analysis).
The FSAR has corrected the description of how structural failure of the turbine building ts prevented from interacting witn tne acjacent Cat ory I structures.
The SAA has revises the explanation of ew eloping techniques employed at CP5ES.
The FSAA now provides an alternative method by which the overturning i
moment for a stn:cture may be calculated.
The FSAR now employs the more conservatne rethodoleg> of % REG,CR 116 3.7.3
- to account for modal contributton above cutoff frequency.
Yhe FSAR has reduced the nureer of nimieum amplituce leading cycles f or tne OBE from 600 cycles to 50 cycles ano frem 120 cycles to 10 cyc for tne SSE for ASME Coce Class 2 ano 3 piping systems only (now con-sistent with hJREG-0500).
The equivalent static load method and simplifiec cesign retnod i
i SER) for analysis of Class 2 ano 3 picing systems are :etn casec :n static seismic analysis (so snealc not ce listee as se:arate setncc-alogies un ;. 3-17, 5ER;.
-*-=*=---,--m__,
- - i I
1
. Sec' ton 3 (continued) t 1.1.3 (continued]
The FSAA has changed the superstructure response spectra for the steam generator support (previous figures have teen superceded).
The FSAR has enanged the oescription of treatment of torsional effects of eccentrte masses in piping analysis.
FSAR Figures 3.8-1 & 3.8 9 have been revised to reflect tne 45 0u11t conftguration.
The statement in tne SSR that "load continations in FSAR are nere con.
servative than tnose specified in SRP 3.4.1" is no longer true (R130.28).
The FSAA has changed the active dynamic degrees of freedom fres 27 to 23 for the vertical seismic model for the Aeactor Internals cased on setsste qualification reports.
The FSAA has changed from 17 to 12 modes present with frequencies less than 33 Hz for the horizontal seismic accel based on seisate qualification reports.
The FSAR has been riviseo to include major computer programs used by f
SWEC for design validation at CpSES (STRUCL.SW, SHELL 1, TIMMIS6, SSMMI).
1 The FSAR now lis's exceptio.'s to CC-2000 of ASME Code Sectior 3, 3.8.1 Div. 2 with regaro to conertte materials.
The criteria in Section 11.10.3 of ACI 318 71 was used for punching).
shear (1973 revision of ASME/ACI 359 did not address punchin9 shear The criteria in Appendix A of the ACI 349 76 Code was used in deter-mintng thermal stresses (ASME/Act-359 does not provide guidance in
]
catermining thermal stresses and ACI 307 is not applicable to the concrete containment structure).
The staf t needs to ver;fy acceptability of an exception to AISC Spectf t-cation Table 1.23.5 for pretensiontng of high strength bolts (for j
example in thermal connections to allow movement between the con-nected parts).
The staff needs to review th a.e 3f kl.2432 in lieu of CC 2612.2 for cheatcal analysis of =*M -etal test.
l The staff neeos to review the use o' 1100 aluminum to be used as a flux without a chemical analysis of each batch, at stipulated by CC-262:
The staf f needs to review the use of alternate methods and requirements (Charpy V. Notch impact test temperatures; CPSES preheating requirements stud welding equipment) to meet intent of the ASME code.
The staff needs to review the use of alternate non. destructive enam-t ination and acceptance standards,
)
The FSAR has changed the avscrtption of the design and analyses pro-i cedures used for the concrete containment structure based on the l
reanalysis performed as part of f.he design validatten for CPSES.
j The FSAR has taken an exception to the 1973 Edition of ASME Coce Section !!! Otv. 2. Subsection CC (CC-3750) for Ui examination of the liner plate in tre vteinity of attacneents.
J Ine FSAR nas reviseo load equations and acceptance criteita to be con.
sistent with RG 1.57, The staff reecs to reference the sLplicable ACI or A.SC s;ecificaticn 3
i in tne writeup 'or tnis SER section.
I i
l 1
I
-_____-_,_.--_-,,._m
Sociton 3 (continued) 3.8.1(continued)
The FSAA now provides a clear description of how RG 1.19 is cceptito with.
The FSAR now allows for use of NB 2432 in lieu of CC.2612 as ;rovicea by appropriate CPSES specifications.
ine FSAR now allows the engineer to review post.neld hest treatment records in iteu of CC 4552.2.2 requirements of an inspector's review.
The FSAR now references RG 1.29. Rev. 2. 2 76, vice Rev. 1, 8 73.
The FSAR now provides the torrect ASME code appitcaotlity cate arc sections used for tne construction of the containment liner and penetrations.
The staff my want to incluce primary I. cop Compartment Walls, unten 3.8.2 is another mejor element for tne contatnment internal strdctures in t
the SER for this sectir.n.
The FSAR has revised the ciscussion of load coreinations for polar crane deratlment.
The criteria in Appendix A of the ACI 349 76 Code were used for determining therral stresses (ASME/Act.359 does not provide guidance for determining thermal stresses and ACI 307 is not applicable to the concrete containment structure).
The F5AR has included "Specification for Structural Joints ustog ASTM A328 or A490 Bolts" as an applicable code.
The F5AR has changed the description of the design and analysis pro-cedures to t:orrect inconsistencies and reflect new methodologies for structures instce containment which were used during design validation activittes.
The staff needs to reference appitcable ACI or AISC specifications for
~
this SER section.
The FSAR has recieved reference to Appencia A of the ACI 318 71 Code (ACI 3181s intended for coesnercial buticings).
The FSAR has included a provisten for the standard detail for develop-ment of reinforcement using a 90' hook not being in accordance with Chapter 12 of ACI 318 71 (exception cased on test data simtlar to aCI 318 83 reduction of cevelopment length).
The FSAR has revised the etscussion for outdoor seismic Category 1 i
3.8.3 tanks to clarify text anc rase discussions consistent with analysts cone in design validation effort, The FSAR has revised the technical discussion regarding cesign and l
procedures to cate discussten cor.sistent with analysis core analysis in the design validation effort (other seismic Category 1 structures other than tanks).
The FSAR nas incluced alternative design criterta used for trackets and corcels =nen considering snear stress.
The staf f reeds to review tne treatrent of mascnry clock = alls (4130.35 WAC (visual weld acceptance criteria) for uncoated.eles.ere sc.
cepted by staff. The staff neecs to revtew saeple inspecticns (Txx.6gC9 cated 11/20/89).
The staff neecs to reference the applicael) ACI or AISC specification for this SER section.
1
. Section 3 (continued)
The SEA needs to address how the issue of seismic gap was accressed 3.8.4 by the CPRT.
3.9.1 Need to reflect that $$ER 14 adcresses non N355 piping up througn FSAR Aeenement 61.
The SER needs to te revised to address the altatnation of artmary coolant loop Dreaks as they affect the cesign basis for etchantcal systems and components (as a result of leak before-Dreat).
The FSAP. has revised the values used for percentage carping for reactor coolant pump settate analyses (change from 4t to 2s damotngl.
The FSAR has now rencved tne restriction that prevei.:sd the use of plastic analysis for coce cceponents.
3.9.2
- The preoperational vibration and dynamic effects testing program needs to be reviewec.
The FSAR has been revised by defining the design basis for vessel motion.
The FSAR provides a ciscussion of the accelerations in the E-specifications covering Westinghouse supplied active valves.
Table 3.9N-10 has deleted RHR$ valves FCV-618 f rom the list since they are designated as for normal coolcown.
The acceptability of stainless steel joints and elbows was reviewed 3.9.3
- and accepted in SSER 14.
The active valve list (Table 3.9N-10) has been updated to reflect current plant valve operability requirements.
The steam generator susunary stress table (Tables 3.9N 14 througn 3.9N 19) have been updated to reflect the latest reviston of the stress report for RCS equipment supports.
Table 3.9N-21. maximum stresses in the reactor coolant loop piping, has been provided in response to Q112.14.
Need to revise the SER to reflect use of code cases N-318, N 397, and N-411 in the design of piping and pipe supports.
The SER needs to reflect use of SRSS method in place in atisolute sus-nation method for confirming peak dynamic respenses of piping systems t
cue to seisste,l.0CA and occasional loads.
Methodology for coactnation of dynamic pipe leads for components unploys the SR55 method endorsec ey m> REG 0484. Rev.1.
I The FSAR has imposed additional requirements to tne analysts of during and after a certain ellential systems to ensure cperactitti plant accident condition (reviewed and approvec ey SSER 14).
The FSAR now contains additional catails on t,ne cesign constceration of a closed system.
The FSAR new allows A!5C supplement for analy:ing structural tubing instrument treulse tuotng supports.
utilizee it, The FSAR new empressely invokes NA 1100 for use of later Ccce Eastions l
and Addence end references the plant $;ecifications fcr the locatien of details relating to Editions, Adcence and Cases usec for Class t and 3 piping systems and supports.
Four Feecwater iypass Valves tair operated cutterfly valves; are added to the active valve list to assure that tney.111 close f or tne f eec;u ;
olscusleo in FSAR Sect:cn 15.2.5.
l Dreat
7-Section 3 (continued) 3.9.3 (continued) Table 1.98 1A has tien revised to indicate that BCP tractive va;ves 4
and components utilize tne loading ccmbuitten specifiec 'er tne applicable plant conditions. ints position applies $RP 3.i.3, Rev. ',
to supercent RG 1.46.
Taole 3.98-18 escanos the normal condition to include Testtrg, s;ecifically, preoperational containment structural integrity pressure test nos subsecuent containment !LRT.
Table 3.38-1C, -5, and -10 have teen revised to reflect plant as-outit conditions.
The drop time of the ful.1 length rod cluster control asseeclies nas E.MES 3.9.4 '
teen revisea from 2.2 seconds to 2.4 seconds.
a The F$AR has revtsee the active velve list tn Table 3.98 10 to re-3.9.6
- flect current plant valve operactlity requirements.
Several tables have oeen revised to reflect deleting the SSE from the emergency conJttien, and define SSE in the Faulted condition.
The FSAR nas revised several 80P systems to provtce overpressure protection ey add'ng relief valves.
4 The !$7 program f t,* pumps and valves needs to be reviewed.
w E.MES The FSAR has removed the AC essential lighting system and CC emer-3.10 gency lighting system from the list of seismic Category 1 instrumen-tation and electrical equipeent which require seismic qualification.
The FSAR states that frequency analysis ray be used for design in place of the "g" ceak (for tray supports).
J10s for 10 no. ESE 40 and ESE-tX (SSER 12) are no longer ap;,licaele because these items will be qualifiec.
4 The values for temperature, pressure and humidity conditions inside sats 3.11 '
and cutside containment have changed (A;pendix 3A Figs. 4.1 4.2, 3A Table 4-1) for botn harsh and mild environments.
a and Appendix heed to clarify the SER to reflect that only certain equipeent and components in tureine building (not wnole turbine butiding) nave eeen evaluated for harsh environment following HEL8s (Appendia 3A i
Table 4 1).
Evaluation is in progress to determine proper flood elevati:n inside containment (SOAR 88 15).
For enesical spray, spray pH and cceposition have changed l
SPL3 (pH of 8.5 10.5 and concentration less enan 2,100 ppes.
TV Electric has coesnitted to the 1976 verston of aSt N18.NU6 i
1 (vice 1972).
Need to evahate changes in equiprent radiation levels inside and outside contaterent (Table 4-1. Appencia 3A). SER new ;resently SPL5 i
evaluates two radtatton levels.
The SER neeas to reflect that TU Electric nas committed to naving all l
safety-relatec electrical equipment quaittied prior to CL s o tore );C' n
ine SER needs to celete Table 3.2 (Itstir.g of electrical eaut; tent with JI0s).
]
The staff Pay want to consicer celeting Table 3.3 fr0m SSER i sed j
reference tne taster toutcrent Itst instead.
]
fne SER r.eecs :o c:rrect Conitreatory ;ssue (14) to :nfir at:r,.
Iss e (idi d5ER ;;. O. 3-W.
a 1
. Section 3 (continued) 3.11 (continued)
The M51.8 superheat issue is still open.
3 pts CPSES now uses 'EEE STO 450-1980, vice 1975 version. 'or :: pi se:e with RG 1.129.
The SER needs to evaluate definition of, and program tor, mile er.
veroceent.
in ac:orcar:e CPSES now uses Cs.137 es we'.1 as Co.60 as test sources s Sptg witn RG 1.89 Rev. 1).
Fecnanical Equipeent review for environe4ntal effects s.:mitted :y TIX-4420 dated 2/15/S5.
The F5AR has revised tre correttment to RG 1.131 for Raychee. Ccro. -eat Shrinkaole Field Splicin.g Systems f or Class IE electric croles.
The FSAR cescribel Pow flooding cut 10 OBA or FELS is addressed in I
Spts the CP5ES System Interaction Program (these changes are also reflecte:
l 1:1 Appendix 3A T31).
1he FSAR (Appenota 3A T3 1) no longer uses the 10 degrees C ruie f:r environmental equipeent cualification.
The FSAR (response to 0140.1) now includes a discussion of the impact SPLS of a MSLB on qualified equipeent outside cr.!taineent.
.~
i SECTION 5 - REACTOR CCOLANT SYSTEM
~
The staff neads to review cout cases on Safety Class 1 ccm.
5.g 1
- onents within tne RCS pressure towncary (response to 00 5.4).
The staff reeds to review the tercerature at which accurulater SRIS 5.2.2 loct. tut is requireo.
i The FS.iR has revtsed the ASME Code editten appitcable to reat;ur 5.2.3 coolant piptng by updating tne Summer '74 to Wir.ter '75 ecttion.
i The sta'f needs to review the !$1 of Class ! systems (Suesect' EMES 5.2.4 leF 1s iedeo to 'nB).
The staf f needs to review tne method for determintng the sump SPLS 5.2.5 level alarm setpoint.
Response (212 32 tnrough 35) identifies the limitations of the SPLS detectors and takes into account minimum sensitivities of the detectors (containment air particulate monitors and radioactive gas monitors) to snow how the intent of RG 1.45 ts met.
c The FSAR has provideo the end.of-life refereice temperature for r
EMT3 5.3.2 reactor vessel beltline metertal.
l The staff needs to review eddy current testitg of steam generators.
[MT3 5.4.2 The staff needs to review the description of neat treatment and 4
tMT3 j
snot peening of Unit 1 steam generator tubes.
The RHR cooldown analysis was redere using ShEC revised heat loads 5.4.3 and service water temperatures.
The staff needs to revtew TU Electric's response to GL 87 12 on t
SA38 RNR purp verteatng during mid. loop operatton (TXX.6749 dated 9/18/8 the applicability of the natural ctr.
[
The staff needs to review SAAB culation test at Diablo Canyon to CPSES (FSAR Appendia 5A).
i t
1 I
1 h
i r
I SECTION 6 ENG! PEERED SAFETY FEATURES The staf f needs to verify acceptablltty of the uti cf cesignated 6.1.1 matertal for ESF piping.
This section need: to cross reference the SSER 3 evaluation of 6.1.2 containrent coatings (Appenoix L).
Need to reflect staff review and approval of TV Electric program for containment coatings performance 171X.4491, TKK.4613, TXX-4653. Tax.6157 NRC letter cated 3/24/87).
Tu Electric nas perferred a new containeent anaissis using 1.EC i SFA.A 6.2.1 LCCT!C computer code because of errors discovered in the ortg3ral jg analysis whien usec CONTEMPT.l,T 26. New information, sucn as the deletion of tne b!T anc revised containrent neat sint data based on current plant drawings ano revised LOCA structural rest transfer coefficient were used ano resulted in an increased con.
tainment peak temperature for the MSLB case. Tables and figures in tats FSAR section have been revised to reflect the results of the revised containzent analysis. SER references to use of CONTEMPT Code for containment analyses are no longer correct.
The TSAR nas been revised to present one smell double ended rupture and two pcwer levels (30% and 70%) instead of the previous two small double. ended ruptures at four power levels (1021, 70s, 30s, and hot shutdown).
The FSAR provides a cescription of the sensitivity study psrformed to determine the effects of varying containment ititial conditions en peat pressure and temperature for the
- EP5G and 9.906 square foot steam tire breaks.
The parameters that were provided as a function of time have
]
been revised, consolidated, and rearranged consistent witn the l
parameters supplied by the LOCT:C : ode.
Theassurptiono{a1/8.inchsirgapwiththermalcorductance i
of 1.6 Stu/hr.f t.'F has been replaced with a more rgalistic t
assuription for interf ace conductance of 10 Stu/hr.f t.'F.
The FSAR has revised the paint heat conductance for steel and t
concrete painted surfaces.
i The LOCTIC code uses the Taganni structural heat transfer coefficient for LOCA analysis and the Ocnics ccef ficient fcr i
MSL6 enalysit, The maximum enternal differential pressure has been cranged j
from 3.37 psid to L 79 psid cased en the conserwative revtsten l
l to the initial containrent pressure.
i The Westinghouse mass and energy release rates for the ;ost.
reflood pease are mocified as discussed in the sroken L:cp and Intact Loop Gererator Analyses.
In addition, the nass ard j
energy release rates have eten rodtfied to incluce core cecay
[
nest and safety injection ficw.
ECCS spillage is accounted for separately cy tne WCT:C ::ce y
N since it was not incluctd in tnt aestingneuse dEILCCC CaICula.
19Cn of mass arc energy for the reflecc phase.
,1 4
i r
I
2-Sociion 6 (continued)
For the MSLB events, the statement that containeent spray SPLS.
actuation occurs within 60 seconds of contairrent pressw e reacning 20 psig nas been replaced atta an expandec desertptien of tne time it takes to achieve full containment scray fIc..
The two cases are the full double ended rupture case anc tne partial double ended rupture / split break cata.
Tables 6.2.1-2; 6.2.1 2A; 6.2.1-3; 6.2.1 3 A; 6.2.1 36; 6.2.; 4 SELS tnrougn 6.2.1-6; 6.2.1-8 inrough 6.2.1 10; 6.2.1 !0; and 6.".; 5;A nave seen revised to reflect the revises containment analysis l
using the LOCTIC code.
Figures 6.2.1 1 through 6.2.1 3; 6.2.1-g through 6.2.1 17 ; and i
Si 3 l
6.2.1 20 nave eten revtsed to reflect the revised containment analysts using tne t.CCTIC code.
The FSAR nas taken an exception to Ah5! N45.4 by ustn? the 6.2.2 alternate eethodology of ANS!/ANS 56.8 1981 for ILRT (simtler changes in NRC letter dated 8/23/84 and $$ER 12, Section e.2.5).
The staff needs to review NPSH curve for the containment spray system.
The FSAR nas added the pressure at which the water test (Pa) is 6.2.3 to occur.
The FSAR nas changed the operation of M5!V bypass valves to. local ranual (ref. TU Electric letter of 12/4/46 in response to RAI of 2/27/86).
The F$AR has changed the isolation criteria for turbine-drivei auntliary feedwater pump warm-up bypass lines.
The FSAR nas celeted the requirement to leak test reitef l
valves as an tsolation bouncary if they relieve into containctnt.
Local vent, drain and test connection valves are not in-cluded on FSAR list but have special reasures to ensure that l
containment integrity is maintained, The staf f needs to review the acceptability of a pressure gauge i
eetween containment isolation valves.
The staff needs to review the acceptabiltry of thereal relief I
valves as a containment moundary.
The FSAR has changed Section 9.4A concern as the design pressure of this containment pressure relief systm to 1.5 pste to te I
consistent with the containment cesign Ortssure criterti.
I The FSAR has revised Table 6.2.4 3 to cesignate tne f at ti.re i
mode of a nuseer of valves as Fail-As-is, The staf f needs to resolve the incersistency tetween the FSAR 3F;5 5.2.4 and SER on model used for zirc-nydrogen reaction (1 !t vs it).
The F5AR nas revised Table 6.2.5 5 to reflect current system SPL3 enanges teenttfted during the comcustible gas centrol review.
ine FSAR nas provided the alternate retnodology for ILRT of Ah5! 8).8 (similar changes accepted by staff in Irtter of 5/23/64 6.2.5 1
and J.2.5 cf $5ER 12).
The staf f reeds to revtew the exerctico recuest of 1/20/56 for a[
i pe/sonriel airloct testing eterption to Apperdia J.
. Section 6 (continued)
The FSAR has changed the power supply for accumulatcrs (cr,aaers 6.3.2 npw lockea out, vice centrol room key lock sniten).
The RW$T alignment in Mcces $ And 6 reeds to Oe Ptviettc.
$RIS 6.3.3 The staff needs to verify acceptability of chlor 1re inlettage 6.4 in tne plant specific analysis (600,:S results in 0.;25 inen p
=ater gauge over-pressure).
The FSAR nas taken an enception to RG 1.35 (i.e., don't assa. e
?
{
A concurrent LOCA and chlorire releaseJ.
The FSAR no longer specifies that a signal from the ;lant vent 4
stacks 15 used to switch to the recirculation rode.
The FSAR has deletec tne statement that smoke detection in tea
\\
control room air intake causes the control reor MVAC system to autcratically shif t to the isolation code. Upon detection of
%(
smoke, tre control room ventilation is r.anually shif ted.
g The FSAR has deleted the outside makeup air ficw etaturement y
_)
y, y
discussion.
The FSAR added the operator radiation doses to Table 6.4.3.
The FSAR has recefinto tne,
trol room pressure envelope
"#/
~'
rooms and areas.
The FSAA has taken alternates to positions in RG 1.52 which Spg,g/pRps 6.5.1 the staff needs te review.
The staf f needs to review the acceptability of a 2-region
.5.2 (sprayed, unsprayec) vs. 3-region containment spray redel.
pRyo The FSAR has revised Table 6.5 6 tasec on the Westinghouse, "Raciation Analysis Design Manual, Standard Plant Model 412,"
a Rev. 3 as applied to CPSES.
The FSAR revised the opening time of the spray pump isolation valves based on controlled throttling of the discharge flew rate to prevent the containment spray pump runout.
The FSAR has revised the Containment free volume from 2.985 million cubic feet to 3.031 million cubic feet, effective PRro sprayed contair. rant voluce from 1.725 million cubic feet to l
1.717 millicn cubic feet, ano the fractional volume spray coverage from 57.8 percent to 56.7 ;ercent.
The FSAR has incorporated the requirer 4nt to perfor1 an aug-6.6.1 mented 131 in superpipe area.
l The FSAR has incorcorated the requirerent to perform augmented 6.6.2 151 in superpipe area.
L SECTION 9 AU11LIARY SYSTEMS 9.1.1
- The procedures have been changed so that inspected fael eiseents will be stored without poly bags.
The SER needs to be race consistent with tne FSAR descriptten of 9.1;; '
spent fuel pool capacity at tire of Itcensing for Unit 1.
l ing FSAR aeds GOC 1 as it aoplies to safety related porttens of tne SPL3/gtggg9.1.3
- spent fuel cooling and purtftcation systems, The F$AR coletes GOC 3, as the fire protection program does not d'
apply to tMis system.
The F5AR adds GCC 56 as it applies to the containment isolation portton of the system (for the skimmer line).
The F5AR adds GOC 61 as it applies to this system for capability of provisicns for containment of radioactivity, periedic testing,l f rom the spent f uel, reduction in fuel storage decay heat remova inventory under accident concttion, and purification of the pool water.
The FSAR acos GDC 63 as it appites to the monttnrf.9 systems ta 9
detect loss of heat removal, excessive radiation levels, and for l
initiating appropriate safety action.
l The FSAR acds the "wet cast pit" to the list of components served by this system.
The FSAR deletes one loop operation for case no. 1, as a single active 1
f ailure needs not be postulated fer full core unload ($RP 9.1.3).
The FSAR has been revised to reflect a change in sampling frequency of the RCS and refueling canal for baron from every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to datly
[
l (FSAR 9.1.4.2.2).
There have been a nuncer of changes to FSAR Table 9.1.3 to reflect l
changes in destgn, calculations and pre;ect spectfications, and to reflect plant as built conditions.
The FSAR has revised Table 9..
1 for decay heat produced, maximum
)
spent fuel pool temperature and temperature rise to indicate the I
Table 9.1.1 has also latest revised data based on a new cslculation.
been s'evtsee to show the numeer of years af ter the plant 15 Opera-i tional (instead of actual years), since tPe startup cates for Units '.
y and 2 have been changed.
4 Table 9.11 has been revtsed (decay nest, taaimum SFP terperature, 5PLj/dkL84) terperature rise time columas) to tecicate the latest revt$ed data j
Also nas deleted terperatures are time Dased on a new calculatton.
to rise to 180'F for full core unloading and ore cooling loop operatice The FSAR corrects the tout to read "2.5 mrem or less," as per 9.1.4
- Westinghouse radiaticn design aanual $7M 412, Rev. 3 idecimal ;otnt l
[
=as missing).
The F5AR has deleted reference to. CAP 9'93, Reference .f)) :ecause this report is not applicaele to C75ES.
Ine fuel outloing evernead crare nas teen reclassifiec as setsste Category I.
l Tne $ER staterent t et totn reacters.111 rot :e ref ae;ec at t=e sa e tire is not sup;ortee of a com.mittert in the FiAE.
i
)
Section 9 (continued) 2-The FfAR has revised the load ccettnations for the fuel tutidteg overread crane to include OBE anc SSE with lifted Icao. ine loacteg comoinations for the polar crane includes Cit with lifted toad ano SSE without Itfted load.
ine FSAR now states tnat the polar crane nas a mantrum "critical
- Icas of 175 tons (instead of "non critical").
Contrary to SER p. 9-7, the FSAR states tnat the spent fuel randteg tcol and porttens of the fuel transfer system components are not seismic Category !.
TV Electric has comitted to irplemer.t any appropriate acticas icenti-9.1.5
- fied in phase ;! of NUREG 0612 regaroing the handling of heavy leads (TXX 43C6 dated 9/24/84).
9.2.1
- The FSAR deleted the $$W supply to the fire protection booster purps, as the CpSES design no longer includes fire protection ecoster pumps. (SER needs to celete the esference to booster pumps ano as-sociated valves on pp. 9.8 and 9.9.)
l The SER needs to te revisto to delete the 55W back-up source to the fire protection cooster pumps, as $ER 5ection 9.2.1, on p. 9 4, 1st j
paragrapn indicates, the "55W can te used as a back-up water supply for the fire protection booster pumps."
I The FSAR revised various $$W ana CCW toeperatures ard time to cooldown on RNR (see otscussion under FSAR Sectica 5.4.1).
The FSAR has revised the system operating description to relect the operation of both $$W pumps to minimize the corrosion due to stagnation in the idle train under the previous mode of operatten.
The FSAR hat added the use of a toxic non ontetting biect$e for the control of Asiatte clams and corrosion inhibitor in the station service water system.
The FSAR has been revised to reflect both purps of Train 'A' and Train '8' in operation to minimize corrosion out to stagnation.
1 The FSAR has deleted Figure 9.2.2 which is replaced oy Figure 9.1 1 for process flow and Figures 1.2 45 and 1.2 46 for ecuiprent layout.
1' The F$AR nas deleted the epoxy cased lining in ordar to prevent sneet code failure, which can plug safety relatec heat oncnangers served by S5W System.
ine SER needs to be revised to re' lect that botn trains of $$d cperate at all times to etninaze corrosion (SER Section ).I.1).
The F5AR has revised the $$s$ outlet temperature from 122'F to 130'F as a result of normal cooldewn of one unit using 2 55 5 puros 4
and 2 55h5 neat eacnangers to cool the RCS from 350'F to 140*F in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
F$AR Table 9.2.1 has eten revised to: (1) add thermal relief salves for overpressure protection of systems as per tne ASPE Code 3ecticn !!!
recuirerents; (C reflect the celetion of the espanston joint enc eco a tard elect of pipe; ano (i) add vacuum creaters to tae service
.ater system to prevent / mitigate water namer in the system.
1 l
.c o
l 3
Sectior 9 (continued)
The FSAA has reviseo the tire to cooldewn on AkA and revised Cu 9.2.2
- temperatures (see discusr'on under F$AR Section 5.4.7).
The FSAR has acced a rot./y instrument air compressor osctage for tee l
f non. safeguards loop to provice acciticesi instrurent air cacactt.
The FSAR nas addec the reactor coolant post.accicent saroling system l
sarple cooler to the itst of the :cecorents cooled by the non. safety
[
loop of the corconer.t cooling water system.
Ine FSAR nas deleted tne low ficw alarms for the control r:om 41r.
f conditioning Concensers, as the cooling mater flow is regulatec cy refrigerant pressure.
The FSAR has clarified t,at CCW5 Curps tratns A ard 5 control n
switches are located on the hot snutdown panel. CCWS puro Train A transfer switch is located on the shutacan transfer panel end CCa5 r
pump Train 8 transfer switch is located on the hot shutocon :anel, The FSAR has acued nandwneels to the level control valves to the C G surge tant, which provides the capability of providing the rate.uo water in tne event of loss of instrueent air to the control valves.
f l
The FSAR has revised the chilled water system by: (1) cnanging tne l
CCW regulating valve automatic control, actuated by refrigerant pressure; (2) accing the accumulator back up tanti and (3) adding I
valve 'tandwneels for operator action.
The SER (p. 940) refers to the CCW surge tant and drain tant atmospheric vent valves, which have been calated from the FSAR.
The FSAR has enanged tre valve status from "passive" to "active" on I
the CCWS inlet and outlet velves to the ventilation chiller and letdown chiller condensors, necessitating closure of these valves on an "5" signal (FV.4650A and 8).
I The FSAR nas upgraded the CCS flow instrurentation to class 1E to provide isolatton of the CCW to the RCP therinel barrier following In additton, control grade alarms alert thermal barrier tube rupture.
the cperator to a potential rupture of tne RCP therinal barriers.
FSAA Table 9.2.3 has added additional corrosion inhibitors to the I
list of inntbitors to be qualified for use in the CCW system to provide a more effective corrosion protection program for tne CCW l
I system.
j FSAR Figure 9.2.3 has been revtsee to reflect existing system configuration based on the cesign valication program and to reflect j
the as. built system.
FSAR fable 9.2 9 nas changed the analysis of dentrecalized ater to
.f/ECE5 2 3.2.3
- i reflect the latest water enemtstry recutrerents f or concuctivity, I
chloride, fluoride ano silica.
l FSAR Table 7.2 10 nas enanged tre specificatien of reactor tateup f/ECES g water to reflect the latest water cremistry recuirements for l
In sedition, cr.nducttytty, enlortce, fluride, 755. TOS and silica.
tre footnote cn osygen concentration cf the RCS nas teen revisec.
[
The FSAR nas acced a ;aragrapn descrioing the ;rovisicn cf a deallnerali:ed mater transfer purp anich is the prir.ary s:urce Jf f
'tre suppressien mater to tre containreet nose stat 1;ns arc tre deluge p1pirg in Ine CnarCoal section Cf the Centatnrent ;reaccess
[
(
f1Iters.
f I
l I
1 l
. Section 9 (continued)
The FSAR has accec a domineralized ester source to perform tureire l
generator primary flow rate testing curing refueling outages.
l The F5AR has teen revised to clartfy that tne required miniest' quantity of water is availaole during norsal plant operetton to achieve ano eatntain safe, cold snutcewn. This includes Moces 1 t
tnrougn 5 of tre T5. A description of the systems tnat recutre a set smte Category I makeup supply nas been added.
The FSAR has corrected the disenarge location for the =4ter treatment system from the evaporation pond to tre low volse.aste treatment f actitty to eeke it conststent with FSAR Sections 9.2.3 and 9.2.8.
F5AR Figure 3.2 5 has be'en upcated to refleet as butit conditices.
9.2.4
- The FSAR has changed tne sewage treatrent plant capacity from ;0.;;0 spo to 105.000 god, revising the capacity of the treatment plant to reflect actual plant conditions.
The F5AR has changed the requirement for drawir.g samples of pota:1e water from several buildings to a single sample drawn daily, con-i sistent with Texas Departrient of Health Orinking Water Standares, l
Section Y! paragraph A.
The SER needs to reflect that the potable water system no longer r
serves as backup lubricating water for the circulating water pumps.
FSAR Figures 9.2-6 and 9.2.7 have been revised to reflect as butit I
corditions.
The F5AR has revised the basis ft.r heat rates of cooling water SPLS 9.2.5
- discharged into the 551 from one trat's to two train operatton (see
(
ciscussion under FSAR Secticn 5.4.7).
The FSAR has revised the basis of spent fuel pool heat loads (see l
description under F5AR Section 5.4.7).
The FSAR has revised the terperatures 'er component cooling) water and service water (see description under FSAR Section 5.4.7.
The FSAR has revised th& text based on the results from the revised f
safe shutoown impoundment heat load calculation, which uses castrum neat loads in lieu of gradient heat load during the duration of a LOCA l
period (accorpanytng FSAR Taeles 9.2 11 ano 9.2 14 and FSAR Figures 9.2 8 and 9.2 10 have been deleted).
The F5AR has revised various component cooling =ater temperatures t
l SPL3 (see descriptten under F5AR 5ection 5.4.7).
The FSAR has redified the CST high level control. =ntch prevents OST i
9.2.6
- isolattny t=e overpressurization in the event of c:ncenser surge tyThe condenser not = ell
[
makeup anc reject lire on CST H1 Mt level.
is desigree to tne postulated surges in tne event of CST nign j
)
tevel.
ine SER (Section 9.2 6. p. 914). reeds to ce revtsee te celete tre l
t surge CaCaCity of tne CST tecause surge overflcw is routed to e C:n-l center not' melt.
r I
1 section 9 (continued)
The SE) (p. 9 14) needs to te revtsed to reflect the CST useele capacity of 270.000 gal.
The FSAR has revised the instrurent air system design to incor; crate
- 9. J,.1
- tne rotary air compressor and its COP:caents, as aeditional systet I
Also, the corponent description, system o; erst r..
capacity is recuiras.
instrumentation and power sucoly sections 9 ave been cndeges to reflect l
tnis system Jesign Cnange (also see F$AR Table 9.3 1).
The FSAR has celetes tne pressuri:er 70Rys from the F$aR text for ne for the instrurent air system, as these PORVs are nce suppliec ey nitrogen accumulators (a,150 see FSAR Table 9.3 3).
[Cl3/
9.3.2
- The FSAR nas deleted the toren injection tank, as the (p$t$ design does not include it.
The FSAR mas rev tsee the steam generator blowdown on.1tne analysers ECES/444='
to detect specific conductivity instead of pH (also see /SAR Table l
r 9.3 4 Sheet 3).
Tne F5AR has enanged 1,he cascription of steam generator blowdown sarple isolation upon an alarm from the monitor.
In place of only (CES/$PLS
$4mple isolation, it eotes that the outboard sample and tr40 erd process isolation valves close. Manual operation from the contro1 i
i room remains unchanged.
The FSAR nas revisto Table 9.3 3 to show the addition of air. operated valves that isolate the steam generators curing 06As and HiLBs.
i The FSAR has made minor revisions to Table 9.3 5 to reflect the entsttng design of the liquia storage tants.
1 The FSAR has revised Figures 9.3 1 thcugn 9.3 11 to reflect plar.t as.tullt Corditions.
The FSAR has teen revised to delete the automatic start of the reactor 9.3.4
- rake.up water pump on demand f rom the reactor makaVD ControIIer.
2 Reactor makeup water purps 40 not have a safety function and re continuously in norcal operation, watch allows the delet$on of '/de 4
autor.atic start function.
Tre F$AR has revised Tables 9.4 2, 9.4 4, 9.4.!, 9.4 6, 9.4 9 aed 9.4 9.4 10 to reflect plant as-tuilt concittens.9.4 1, 9.4 11, 9.4 12.
ine FSAR has revised Figures 3.4 1 through 9.4 14, and 9.4 15 to reflect plant as.Du1It 40rditions.
i The F$AR hat reviste the tent to clarify tne control recm locat'C6
$9($
9.4.1 '
and the design parareters for tne systems serving the CCntrol r:ce area.
The FSAR nas added tne function of tre aon safety related air.
i 57L3 00nditioning units servicing centrol r00s areas.
TPe F54R nas crarged tne o;erator act'en tt e fr:m e19mt nears 'o f
j
$ P '.5 fan.
- re nour for a : ping one pressur,,ats:e ae. cre f m catien.e,t I
i I
f i
2 l
4 4
6-Section g (continued)
The F1AA has deleted the plant vent stack nign radiation montter spl3 from the primary plant ventilation ennaust. Two reduncant raciatten monitors are provided for each control recm air intake went in Itay of an earlier design enten eepicyed one air intate moniter with tacaup from a plant vent staca nign raciation montter located en the artmary plant ventilation enneust.
Ine SER is no lorger c:rrect ano the phrase "plant vent stack nign radiation signal" needs to te removed.
The /$AA has provided a statement snat tne chlorine detectors are
$PL3 not missile protected. This is cecause locattng the detectcrs within tne protected area adversely effects tnetr operatirg sensitivity. Creelt for'their operation is not tamen during postulated tornado events.
The F$AA has enangee the reference applicable to the iodine
$PL3 adsorters from RG 1.52. Rev.1 to the currently applicatie revision as discussed in Appendia 1A(B),
The SEA (p. 9 21) reflects tact the control room HYAC system has
$PLS provisions for purging of smote or other contaminents with no recirculation by bringing in fresh outside air and exhausting the The F5AA states that pertante L f M contaminated air to the outside.smon '--- --
are ut*d to remove heavy concentrations of conte.
minents (FSAA 9.4.1.3i.
The SEA states that redundant smoke detectors are located in the SPLS control. room air intane (the F5AR 1escribes non reevndant smoke detector installation).
The FSAA has changed the fuel building room temperature during 9.4.2 '
normal condition and adds the emergency condition room temperatures for the spent fuel pool heat eacmanger ano pump rooms (also deleted Teole 9.4 2a).
stem in The FSAR nas revised the operation of tne venttistion sy$A).
A accordance with the resolution of $0AA 44 27 (see HVAC p slight negative pressure is maintained in the fuel handitag butiding Hcwever, ucon during normal operetton or a fuel handitng accident.
the loss of offsite power, the Fht ennault util not te estatainec cy tne primary planet enhaust units, so tats reference nas teen In addition, the antent temperature for tne spent fuel removed.
pool cooling pumps is maintained by emergency fan coil ustts anc the safety.related chtlled water system.
The 75A4 has removed a sentence stating that modulating supply air dampers centrol the slignt negative pressure in the fuel mandling area.
The FSAR has added &n air handling unit for storage reem 25CA in tne fuel handling builateg to adequately cool the ece safetprelated ecutoment.
fne FSAA nas acced a paragesom defintrg tne safety class see ^tsmic category of the 'wel Duticing einault cuct mora, tre emergenef 'an cott units, and the trent fuel ennaust fans.
7-Section 9 (continued)
The $[1t (p. 9 22) States that before refuelirg operationl. the bi exhaust is directed te the 50% ESF ennaust filtratten units, inis staterent is not sucesrted by the FSAR, in f act, current ces);n is a modular ventilation system.
ine F5AR has added eForgency fans for room 100 to provide cooling, 9.4.3
- as ser loss of non. safety equipent ventilation design enange (also, deletec Taele 9.4 24).
l The F5AR has recoved tne reference to the need to moculate auntliary tulletng supply dampers in orcer to rair.tain a slightly negattve pressure anc adaed worcing to Indicate that it is the emergency f an co11 units wnich control the air teeperature.
The FSAR nas revista the section to incluce that a slight negative pressure is also ratntained curing and after a LOCA.
fne FSAR has accea a cescription of the recycle holdup tank compartrents anc the potenttat effects of a rupture of the tank diaphrages.
The FSAR has provided eeergency f an.011 units for each of the various puros recuired for a LCCA. Each compartment is maintained at an amotent ter.perature conducive to the long term operation of j
the eculpeent contained theretn.
The FSAR cefines fourteen exhaust units as non E5F and adds two E3F l
ennaust units.
The F5AR has been revised to add a dascription of the interlocking l
of the supply and exhaust f ans.
The FSAR has upgraced all of the exhaust system up to the fan discharge to seismic Category 1, but 19e reference to Ah5 Safety l
The air supply system is upgraded from seismic Class 3 is dro;ced.
Category (( to Category 1. eACept for the f ans and daPpers which cnarge from non. seismic to Category II.
l The SER (p. 9 24) states that tne re:urrant ESF enhaust units l
exhaust the air thre"gn the auxiliary butiding's E5F filter systems.
This statement is not supported by the F5AR, in fact, current cesign is a andular ventilation systems.
Tne FSAR ha' acetfied the description of the reculation of supply 9.4.4 -
air to maintain negative pressure. Moculation =111 rot ce necessary to maintain the negative pressure cue to fan sizing.
ine FSAR has mootfted the description of tne cceratton of the system treating as one case the loss of of f stte ;cwer togetter utth a LCCA.
I The new descriptien clarifles tre use of the eeergency fan cott units in the E5F ;ur-oces.
The F$AR nas upgracec tne rain air supply system frem seismte Category !! to 1.
The F5AR has acced the functicn of maintaining ar.bient teeperature stove the Iceer limit for scre process piping to the criginal
- ersonnel comfort function of the unit nests.
Ine F5AR MCw states tPat **ep cCrpartTents centaining EST rotor-criven puros =111 nave ererjency fan coil units.
Tnese tot:rs are tPe chief neat jenerators requiring tre c;oling Coils.
e l
8-Section 9 (continued)
The FSAR has separated the specification for the exhaust system to snow some NNS. seismic Category I: construction wnere it cces not interfere with safety functions.
The FSAR nas enanged Section 9.4A concerning tre design 9.4.5 '
pressure of the containment pressure relief sistem to 1.5 ;s'g.
to ce consistent witn tne containrent design cressure criteria.
I The staff nas not provicea a review of tne follcaing systers:
contatement atr recirculation and cooling system (F5AR Section 9.4A);
- control roo crtve recnanism ventitation system (F5AR
[
Section 9.4A);
- neutron detector well ecoling system (F5AR Section 9.4A h l
containeent preaccess filtration system (FSAR Section 9.4A);
- reactor coolant pipe penetration cooling system (FSAR Section 9.4A); and
- plant ventilation chtlled water system (FSAR Section l
9.at).
The staff has provided a review (SER Section 6.2.3) only of tne i
Isolation aspects of the i
- containment pressure rtlief system (F5AR section 9.4A); and i
- containment Durge supply and exhaust system (F5AR Section 9.4A).
The F5AR nas revised Section 9.48, service water intake structural ventilation system, and changes the maximum indoor l
cesign temperature to 132'F based on new calculations.
FSAR Section 9.4C provides the correct function for the diesel l
The description previously t
generator ventilation system.
cescribed tne function of supplying cercussion air but this l
l function is accomplished by the die,el gere.*ator coeustion air intate and exhaust system (see FSAR Section 9.5.8).
The 5ER needs to te revised to delete the system function of providir.g l
cutside str for diesel comeustion.
t The FSAR has clarified the operation of the diesel generator Dutiding exhaust fans.
Sufficient fans are started to ensure acecuate roce ventilation. The numer of f ans operatirg is Itatted during tne winter renths to prevent the room temperature from f alling celce i
t the minima design toegerature (F5AR 5ection 9.4C).
r The FSAR has aeded the description of tme tseletten carcers in I
the NSFW piping area ventilatica system. =htch protects the i
safety relates equi;eert located in the nearcy areas bem Ene effects of M5FW pipe erests (FSAR Section 9.4C).
i The FSAR has changed tne nycrogen concentratten tevel to 2s ;er AN5!/ANS 59.2 1986 (FSAR Secticn 9.4C).
The FSAR nas cescrited the :arpers and *. eaters that Or vice rakeup air and Peating, fo6lowing a loss of offsite 30eer to
)
Faintain tne tattery room under design CtrctttCns sF542 Sect 9Cr 9.4C).
i l
4 i
k
(
l
- l Section9(continued)
The FSAR has revised the indoor design condttions for the security of fice. deleted the numidity requirement and uCCated the temperature to represent the present 45 ouilt Ccnc.tions si!AR 7
Section 9.4C).
The FSAR nas added a non safety related HVAC System for the cee e
Battery ano Charging Room wnicn provices batt uD CC pcmer to emergency lighting in the control roce.
The FSAR has revised Section 9.40 with the following changes:
updated the design parartters of flow and velocity caseo cn l
revised destgn documents; clarified the flew through the vents based on the present designt and addeo the classification of the vent stack as seismic Category ::
and its effects on safety related systems in the event of fatture.
9.4.6 '
The FSAR has revised Section 9.4F to correct the capacity of l
the safety related cht11ers to 101 tons. This is consistent with the project specification ano design criteria.
SER (p. 9 28) states that functional tests and inspection for l
the safety cht11ed water system are to te ini,1uded in the TS.
The changes to the fire protection program that have occurred
- l 9.5.1
- str.ce SSER li: was cubitshed are eeing reviewed by A. Singh (R!V) ano various contractors.
Inspection Reports 50 445/84 44 and examined estabitshment and implementation of the 50 445/87 22 fire protection program and compliance etth the requirements of CPPO will BTP APC58 9.5.1 Appendix A and 10 (FR 50, Appendia R.
coordinate the issuance of the SER with NRR.
FSAR 5ection 7.4.2 has added an additional fire to be analyzed for shutdown from outside the centrol room.
Section 13.38 contains some discussions of the fire protection program.
Txx 6376 and TII 6582 Itst Tu Electric responses to $5ER 12, Sec'.ien 9.5.1.
i Addt'. tonal changes to section 9.5.1 will te tutettted in a future i
FSAR amenoment.
i TheSEN(whichstatesthattherearethreepagingacresforthe 9.5.2 '
public address system) is not consistent with the FSAR ( nich states l
that there are two paging 2Cres. the noministratiCn Cutidinc are t'it l
main plant (unten is furtner sucotviced into 4 tcres]).
The SER states that the PABX tele;none system has 28 trur.a 11ees.
[
This is witneut tests in the FSAR.
The SER credits tre intraplant portabte radio transmitter receiver f
system with provioing ccesNnication tetmetn t*e Control roca Ano etner t
Duilcings.
Tne FSAR does not rate a ccn'iittent to retain a alkie-i taltie in tne control room, aaltte talkies cay :e used p the fire
[
trt;4de and other chief users outsice of tne control rocm.
l i
I
?
-s-
- 10 Section g (cunttnued)
The F5AR has provided a thorough listing of tne site emergency coesnun'ication systems.
The F5AR nas deleted the description of the seund. powered telepnene sy: tem. This system 15 not used as the primary C vunication System for not of Cold shutdcun, as tne intraplant portaole radio comrunication system is used for abnorral anc e*ergencj concitions.
The FSAR has provided a more accurate and thorough description of plant to of fstte emergency telegnone systems.
The F5AR nas addeo reference to rotating team tights to clartfy the type of visual inotcatten provided with the evacuation alarm.
The F5AR describes tne pAge. party /puelle andress system as a backup to the portaole racto system for use by pl4nt operaters during hot snutcown for technical accuracy.
The 85AR nas been revised to add information and references g.5.3 '
concerning the illumination level provided by the AC essential lighting systems and DC er4rgency lighting systess.
The staff needs to revtse tne SER to reflect that AC essential anc OC emergency lighting systems have been reclassified from 1E to non-IE (DC energency lighting now has o.:n batteries).
The staff neecs to review the F5AR description of lighting levels.
The staff needs to review the acceptability of fixed flourescent bnits.
The FSAR has revised reference to the IES Lighting Manabook to 1981 application volume.
The turDine building tattery pack lighting is rated for four hours.
Due to reclasstftcation from 1E to non.it, testing of the AC essential lighting system will not be c:nducted curing periodic ECG loading test.
The F5AR has clarified the system description for filling, venting, 5FL5/flcG9.5.4*
draining anc removing concentate from storage tanks, per as tutlt conditions and in coepliance with HEC Regulatory Guida 1.137 and Ah5! N!95.
The F5AR reflects replacement of simples strairers with duplea Spte/844) ter reroval capability elimina.es tne stratners. This update in (1 5 clegging of filters and teproves the avatlabiltty of quality onesel fuel 01i supply ';o the atesel generators.
l The F5AR has revised the fuel ott day tant capacity fecn 4-1/2 neurs SPLV4426 to useable capacity of 3 neurs of continucus operation of diesel generators at rated 1C05 load. This escoeds the requirerents of NRC Regulatory Guide 1.137 anc Ah51 N195 (65 minutes of continuous The FSAR has also celeted the tara capacity in gallens cperation).
as it varies =)Jh the density Of fuel cil.
SER (p. 9 39) neecs to m!/8 4 I'e"llU'hiesietedtnereferencetothedieselgenerat:rfueiou eoester po, ae rotor e nen engine p.rp, and in, moiar, o.:e oil put; cwring emergenC) operation of the ECG.
Ine F5AR nas replacee tne vacuus sures.tth centrifugal of:.ers SP.5/Ec 4 fer diesel gererator tran* Case ventilat1Cn to provide ;0sithe teams of f orce4 tentilation Infough the Ctesel gererator
- ranacase ans :: ref'ect tne as cutit :enettiens.
l
1 11 -
Soution 9 (continuec) 9.5.4 (continued)
FSAA F4gure 9.5 5 nas eeen revised to add the following:
SPLS/dECJEdb note for rer. oval of strainer elecent from Y strainer; duplex stratner as per requirements of ANS: N195; day tant vent pipe vacuum breaters which er *ocated in the misstie ;rotected area and seismically
.;orted; and m15cellaneoul technical and editorial charges to tre figure to make it consistent with vendor drawings an01soretric drawings.
The SER 15ection 9.5.a.1. Dage 9 39. taragraph a) needs to te revised for venting ccPDonents unich are seismic 4Ily SWCDorted, but are not A5ME 5ection III. Class 3.
Missile protection is provided for vent paths.'
The SER (Section 9.5.4.2. page 9 19 paragrapn 5) reeds to te clartfied for the exceptions to Regulatory Guide 1.137.
The FSAR has revtsed the fuel oil monttoring program to conform to. current standaros. The revised testing will test the parameters which indicate degradation or contamination of fuel curing transit ( ASTM 0975 74 ts updated to ASTM 0975 41 and ASTM 0270 65 is updated to ASTM 04057 81).
$ r The FSAR has deleted *30% diesel generator set efficiency" and gpq ggp/ggggggg replaced it with "Fuel Consumation based on test data".
g The FSAR has deleted reference to the motor driven jacket water JD8 J 9.5.5
- pump, which is not available during emergency operation of the e F Need to update the SER (p. 9 40).
EDG.
The SER (p. 9 40) needs to delete reference to GOC 17.
l v
The FSAR has deleted _ reference to the retor driven lube oil pump Spts 9.5.7 *
[
which is not evallable during emergency cperatton of the EDG.
Need to update the SER (p. 9 43).
The staff needs to revtew responses to NUREG 1216 for 70( diesel SPL5/SELS 9.5.9
- engines (TIA 6236). See $5ER 6. Section 9.5.9 and Appendia 1.
55[R 12 Itsts this as Outstanding issue (32) and as Ltcense Condition (15).
1 L
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l
SECT!ch 10. STEM AND POWER.CONVER$iCN Sf 5 FEM FSAA Table 10.1 1 nas enarged the turetne generator outout to 19.1 1.203,378 K. with valves wice cpen. Tmis Change represents ACCut a Q.2% fncrtait.
- e F5AR re#1= cts tnat the 9010 copper nicks. alley N5R twee
$FL3gt.df.2 euncles and tute smeets nave teen replacec with ferrittC stelnless steel twees and inconel clac careon steel twee snetts to provvet degracation of steam generator tubing.
The F5AR states that cre rain steam aac one Icw. pressure stcc.ana.
10.2.1 '
control valve =t11 to in'spected every 40 months and tnat all valves will te inspected witntn 10 years, as requirea by tech specJ.
10.2.I
- The FSAR nas been revised to correct the statement "the htgn. pressure It is now clear that tne nign pres.
turetne cannot generate missiles."
sure turetne can gererate missiles, but tr.ey are counced by tnt kw pressure Curoine miss11.
The staff needs to review TV's letter (T11 4512 cated 7/15/85)
EMTS wr.ich seeks to provide tasts for removal of License Conettien (4) in t
55ER 12.
4 SSER 6 states tPat TU will conduct a visual and surf ace examinetton EMT3 of the turetne etses every 5 years. The F5AR (Section 10.2.3.6) states that visual inspections will te conducted at refueling snutdowns at intervals not to exceed tnree years, The FSAR nas upcated the main steam sistem design parameters baseo i
57L3 10.3.1
- on tne design calculations.
kSA16/fAdid' Tne F5AR nas changed the Iteitt on stear generator
'g tion 10.3.1 and Table 10.3 3).
The FSAR adds safety related at-accurulatars for SG PORYs. as the
.T p corpressed air system ts not safety relaf ad.
ine SER states tnat SG PORVs are providr1 with nitrogen accumulators i
ano needs to et corrected.
Ine staff neecs to cceplete its review of the enange in PS!Y ty; ass
!ssue (27; l
valve operation to e.anual (tnis was 'isted as Confirmatory in SSER 12).
r Ine FSAA states that the M51v typass salve util te locked closed cu.
ing poetr operation. ints replaces a cerettrant f or a cvstgn to stcp i
flow in ettner direction.
The SG PORVs are required to nave tne capactitty to te operated re.
motely from tne control room followteg a 55E. coincicent ith t*e.00P.
fne SER reees to ee revised to delete discussion of closure of M S
A Dypass valve closure tire upon receipt of MSIV closure signal, as tnese valves are nc= renual.
45;( see11 as
\\
5 M /S MTS
- fne FSAR w; cates tne 'tycrostatic test pressure of the :
emo valvei.
Ub b@
ime F5AR ras clarifiec the mycrostatic disc testing 45 ;er A$ME !)Ei C:ce. sects:n :::, ;4ra; n;a si ;i31.i;c,.
1 d
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2 Section 10 (r.ontinued) 10.3.1 (continued)The FSAR has changed the Main Steam Safety valve ele =cc=n to u of tre
-t*t?" h g 4 set pressure of tne safety valve. 45 ;er a5ME 9&PV Cece, Sects:n ;;;.
Subsection NC 7614.1 and Specification 232J.*S 77, Rev. 2.
The F5)R nas changec the raterial classification of nonpressure re.
\\
ID taintag Cor;enents of tre M51Vs to ratch tne design.
\\
TPe F$AR nas enanged the secondary aster emet.tstry to Igree a$tm ;*e l
IDIO
~
\\
recorrendations of the iPRI Cuners Group for optimum ;erf oreance of tre steam gererators.
l the 5tR (p.10 4) states tnat the plant can et trougnt to cole so ut::.n N3 9 43 from the control room using Jnly safety. grace recnamical and electric 4:
\\
systems in the event of LOOP or loss of instrument air.
i M51V actuators are desto.ned to ASME 8&PV Secticn V!!! in lieu of A
IA4E4 A5ME B&PV Coce Section III as per ASME Cede Section !!! sutarticles M
NA.1140 and NA.1130.
The 5tR states (p.10 6) that low r tloy steel is not uttitrea fer rain 10.3.3 '
Steam or f etcwater system corponents and that RG 1.50 is not apoltcat te.
low The FSAR, however, states that preheat temperatures for weldtej. 2).
alloy steel are in accordance with RG 1,50 (F5AA Section 10.3.
The ausiliary steam system, tae estraction steam system, the turbine 10.4 oil and purification system, and tne turbine plant cooling nat,er system are not addressed in the SER, but nave undergone changes since tPe
(
last review of the F5AR.
The FSAR reflects the inttallation af titanium tube bundles (ferrerly l
-444 knm(0.4.1
- copper.ntese) alloy), and titantum clad carton steel twee snetts (formerly alumteu$.ttsis:e), in tne Unit I and 2 matn condenser stells l
\\ scgg y'
to Irprove t*e ability of condenser t.:es and tute sheets to resist long term corrosion, erosion or stress cracking.
\\
The new leak.ttght tube sheet design features solid tube snetts in ad.
8 S/ 4.6 dttion to welded tute.to tube sheet jolnts, unich results in deletion j
\\
of the tute sheet pressurtzation system.
), W 10.4.5
- The FSAtl reflects the installatten of tttarium tube tuno'es (for-erly c pper.61chel alloy), and titantum clad carten steel tute sPeets
}Q (forMPly aluntnum.bronte), in tPe 'init 1 anC 2 tain Cordenser 59 ells g
to Irprove the ability of concenter tutes and tute snetts :o resist f
a long tern corrostun, erosion or stress cracaing.
ine FSAR indicates snat snere are no ;erfuerance tests icentified for N
l S/'Le the circulating water system tutterfly valves. Continued reintenance ac'ivittes assure proper functioning of tre valves anc vehe :;erators.
The FSAR deletes mention of the spectfit amount of cnlortre ad:ed, as 5;LS/fC.Ed concentratien deseeds on the location of tre strole ressuretent.
ine NPCES ;ermit limits chlorire to 0.2 p;m, avera;e, and 0.5 ;;m, raaimum.
- 3*
Sect. ion 10 (c:ntinuec)
The F5AR has added the NRC Reg Guide and AN51 Standard a;plicasie 10.4.7 -
to the Condensate ard Feedwate. 2pstem.
The F5AR has adced tne MSR separator crain tant (=P' s provices Condensate to the system) to the ctscunston.
The F5AR has revised the useable volure, ces'gn vo hre anc the volumt for emergen;j availaellity of the Concensate storage tant use of tne aid system.
The 85AR has revisec the useable volu e of 270,0C0 gallens peecs tu r
se reflectec in the SER, =nten new states 276.000 gallens).
fne FSAR has teen revised to acd a cescription of the full flew flushing operatttn.
The F54R nas revisto tne cescription of tne 53 sarolteg systen ::
celete reference to !Gs 3 ard 4 (sarple lines were cappto).
Tre F5AR has tven revised to acd the classif tcatien of the cwecensate Seiselc Category !!g in the Saf eguards Building (non ruclear Saf anc feecwater pipin s.
The FSAR icentifies condenser not well low level as an addttteral tric for the COnder!. ate purps.
The F5AR Identifies that transfer from the feedwater control typass valves to tne feeciater control valves is ranwally intttated.
The F5AR nas race nurerous enanges with reg wi to the feec=ater SPL8 isolation vehe as a result of concerns regarding water namer ans SG vibratton issues.
The F.'sR nas teen revised to replace the feed 4ater bypass tarpering SPLS the feecwater split ficw bypass valve.
val ; with fn? FSAR nad erotfied the controls en tne feedwater isolatian bypass vahe to remain closed instead V autocatically open upon lack of water nar1rer permissives.
ine F5AR nas addeo AG 1.32, 1.47, 1.53 are 1.75 as appitcable to tre condensate ard fetcwater systems.
The F5AR has been revised to indicate that the FISV is r4nwally opened to purge pockets of colf water. split f r:e 10:10 (at 4011001 lead) to The F5AR nas changed the flew 10:10 at ICC1 load and screwnat less tnan 90:10 frem 50s to ;CCl lead Spi 3 to raten the as butit systew.
The test A water narr4r test has even addec to F5AR 5ection 14.2.
report demonstrating water namer adequacy is available en site f er SFL3 The staff needs to review tne results and if fewed acceptatie, review.
recove restriction cited in 55ER 4, p. n 12.
f ne F5AR has acded fcur Fee 4=ater Sypass vahes (41r crersted tutterfi f vahes) to the active vahe list to assure that they mill cl0se f 0P tr 5;t3 feedline break.
ECES 10.4.t.
- The FSAR Pas enangec the SG dic.cc.n.ater cremistry 'o -atsn the and witncut a latest evaluaticn of the articipatec c:rcitions.ith leak f rom the ;rirary side. This change Oeletes free Fycroalce ?r:m a
totn analyses, and hydrattre anc ror;Poltre frem the analysis.itaout leat, and eitminates tre estirtate of particle site.
Ine FSAR returns to the original esticate (Or $1 at less than ; gi; Tne FSAR Pas accec air creratec ve hes in place of -c':r ; a rates h
wo bes to ?lolate $35 curirg CSAs and -[Lis.
FQP the PCn safety relates ;;rtion of SG c:c.cc.n, tre !!R i-site >
1"I r6.d.er, t*e F51R s;ec tf t cally irc$ cates ;;5[1 Inst 43 1.la) 15 *4t.
3a:
cces Qt c;r.~'t !? 33 !.'.4; t;r Inis ;crtien af $5 : ;e;c.n sjste?
- s *et.
A 5'* E, S e c t i p i...
~
.4.
Sectaan 10 (continueo)
The F5AR has anded warm wo valves ano steam supply cypass t hes te SPLS 10.4.3 '
the TDAFW pues to pre.=4rm tne steam supply 11res to minisuge transtant effect curing 70AFd pur.p survettlance testteg (see also A
FSAR Figure 10.3 1).
The F5AR nas acceo safety related accueulators to steam va!vts for *.ee TCAF. ;a e to permit valve closing for centainment 1 solation or to r
isola'.e a depressurttec SG.
Tre F5AR nas changes tne cesign parareters for the AF. cr.poret ts based on tne cesign docusents, certified pumo curves an4 d.51F 10.1.
ine F5AR mas stated snat the AFw cesign basis ts (1) a nours coeretier at hot stanoby in ti.e event of onsite/off stte power av1114cle attn single failure, and (2) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of operation at not stansey in tne event of :.atn steam or feecuater line crests.
The revised useable voluine of 270.000 gallons neads to to reflectec i
l in the SER (which etw states 276.000 Ja11ons).
i The F5AR has revisto the AFm system description with regard to nurter of pumps ;urp capacities, and discharge pipi 1 configuratton.
The F5AR nas accid a discussion of the AFW system perfor1hy.e cuf *.Pg a large treat LCCA.
The F5AR states that eitner both motor. driven pumps or the turetre.
ortven pump alone is required to take the plan to safe snutdown.
l The F5AR states that, cepenaing on the severity of the event,*either the two motor. driven purps or all three AFW pumps auto start.ollowing i
a M5LB or a FLB.
The FSAR has added Ah5 Safety Class 2 for the AFW systes containment e
penetration councary and a connection to fetevater.
l Upon autoestte inttistion of the AFW system, isolation of SS blewdown anc !
l sampilng for all SGs occurs.
The F5AR adds high flow to auto trip of the f1 w control valves f rom manual flow control to automatic pressure control to protect the l
pumps (now requires low discharge pressure and high flow).
l The FSAR has teen revised to toentify inat the TOAFW turstra has a f
rechanical/nydraulic governor in lieu of an electronte governor, l
5tR 5ection 10.4.9.1 needs to be revties to reflect F5tR isolt 10.4 8 i
The FSAA has been revised to te consistent with the mistinghouse re.
r cuirteents that pure response ce D& sed on the receipt of an actuation i
signs 1.
f i
The FSAR mas deletes the ice suction gressure trip to prevent a spurious low pressure stqnal from tripping tne AFa' system.
Ine F5AR has been reviste to reflect CST alarms for n;.e!, LO. and j
d 1
LQ.LO.
The F5AR clartfies that Ice etscnarge pressure alerrs are only ;ro.
l SFL3 l
vided fui tne rotor.criven Afi pumps.
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O SECTION 11 - RADICACTIVE nASTE MANAGEMEtiT SPLS/PRP'S 11.1 TU has, taken an exception to RG 1.109, Rev 1 in that an 8-rrontn cow grazing season was assumed.
The SER and FSAR Acurce term tab'es for both liquid and gaseous 3
effluents are not consistent. Review anc rewrite may ce necessary.
Staff needs to review 00CM (TXX-88593 dated 8/8/88) and future occate.
1 A cnange to the Resin Disposal System to allow bypassing of tne 11.2.1
- Spent Resin Storage Tank (to allow for maintenance and recair; nas been made.
Relief Valve l'nP-7176 has been added to the drain system to provide overpressure protection.
Inlet Isolation Valves XWP-221 and XWI-222 have been added to their respective floor crain tank strainers.
Relief Valves XWP-318 and AWP-320 have been added to drain channel B.
Numerous figures have been revised to reflect as-built conditions.
A clamp-on flow indicator monitor has buen added to the domineralizer water tank.
The SER states, "All liquid waste is processed on a batch basts." The FSAR, however, indicates that the reactor coolant drain circuit is an exception to the batch processing method used for the remainder of liquid waste processing system.
The SER maximum individual dose tables are not consistent with the FSAR.
The SER now contains discussions of limits and surveillance to be' con-tained in the tech specs. These requi. ements will instead be contained in Radiological Effluent Environmental Monitoring Manual (REEMM).
SER section 11.2.1.3 needs to clarify that CPSES did not connit to RG 1.143.
The steff needs to review the discrep6ncy between the FSAR and SER section 11.2.1.3 for liquid waste release of tritium anc radioactivo materials.
11.2.2
- The radwaste monitor alarm setpoint has been raised from 0.155 to 0.25t hydrogen to reflect as-built conditions.
The description of the operation of the Ga; ecus Waste Processing Sys-tea. has oeen changed for low pressure and h1gner pressure operations.
SER Section 11.2.2.5 needs to clarify that CPSES did not comit to RG 1.143.
The staff needs to rJview the discrepancy between the FSAR and SER section 11.2.2.5 for releases of gaseous ro:=aste.
11.2.3
- FSAR page 11.4-5 clarifies the description cf containers used for shipment and disposal of radicactive wastes.
The Process Control Program needs to 5e reviewed (PCP senedulec for submittal in October 1988).
Staff needs to review estimates for offsite sniprent of solictfiec wet waste ano dry solid waste.
Additional solid radwaste storage capacity for Unit 2 ts an out-standing issue from SSER 12.
11.3 The staf f needs to review FSAR Tcble 11.5.1 and text nien nave :een cnanged to update the design and reflect as cutit concitions.
4 A control room CRT display for digital ractation. onitoring system t
SPL3/PRPS nas caen acced to the console.
s SECTION 15 - ACCIDENT ANALYSIS The FSAR (p. 15.0-19) provides clarification that fission product 15.1.1
- cecay energy is based on core average exposure at the eno of the equilibrium cycle.
The FSAR nas revised Figure 15.0-1 to reflect previous enanges in SRX8/PRPS increased error allowance associateo
, nominal reactor coolant T,in,strumentation and an increase in the A
with h-16 core protection low pressure core safety limit.
The staff has still not reviewed the use of LOFTRAN and FACTRAN for SRX8/PRF8 15.1.2
- The staff approved the Westingnouse topical reports use at CPSES.
on LOFTRAN and FACTRAN in the SERs, issued on 7/29/83 and 9/30/86, respectively.
Source terms for primary side equilibrium activities (FSAR Taele SRXB/PRF8 15.1 a) have been revised to reflect use of tech spec limits (on RCS activity) an( design basis gap activity.
Source terms for secosidary side equilibrium activities (FSAR Table 15.1-a SRX8/PRPS nave been revised to reflect use of 1 gpm SG tui:e leak and liquid and steam pnases.
Staff needs to resolve inconsistency between SER and FSAR.
15.2.1
- F3AR indicates SER (p.15 a) states ONBR oid not f all below 1.4.
DNBR greater than 1.3 or DNBR much greater than 1.3 (FSAR Sections 15.1.2.3; 15.1.3.3; 15.1.4.3 and 15.4.4.3).
For loss of non-emergency AC power to station auxiliaries and loss of SRXB 15.2.2
vised to reflect a lower AFW flow rate. These accidents will be further revised in a future FSAR Amendment, considering a different single failure.
Other accident assumptions for loss of non-emergency AC power and SRXB loss of normal feedwater flow have been changed and need to be re-viewed by the staff.
FSAR Tables 15.2-1 (Sht 5) and 15.2-1 (Sht 6) and Figures 15.1-9 tnrough 15.1 12, sumarizing the results of enese accidents, need to SRXS oe reviewed.
Rcanalysis of the turbine trip event has resulted in revised transients SRXS for certain parameters.
Rod Cluster Control Assernoly Malfunctions (15.2.3.3) were misnureered 15.2.3
- as 15.2.2.3 in SSEk 6.
The FSAR has been revised to reflect an increased CVCS leat rat SRXB/PRPS 15.1.1
- ICC gpm to 190 cpm.
Ine FSAR nas oeen revtsed to show detection of leak is by icw pressure SRX3/PRPS alarm, vice nign radiation alarm.
The FSAR nas restsed the tire to detection and operator action to less SRXB/PRPS than 30 minutes, vice detection witnin 7 minutes.
The SER incorrectly cross references 15.5, anen it snnuld reference 15.3.4 '
.i.4.2.
O g
1
. Section 15 (corpinued)
Automatic NS!Y bypass valve actuators were replaced wit 5 manual 15.3.5
- actuators which are locked closed during power operations.
15.3.6
- The FSAR has changed the assumption for average coolant temperature in SAX 8/PRPSf double-endeo rupture f rom +5.5'F to +6.5'F.
Spcg The initial pressurizer level 15 51, vice 2%, above nominal program va ke.
m a-
"n FSAR nas used more conservative initial water levels in tne faulted Intact SG (5s nigher in the former and 5% lower in the latter).
and The FSAR now assumes 430 gpm ficw from AFW system, vice 470 gpm.
The FSAR has changed the assumption used in the analysis of the largest FW line break for FW line purge from 750 seconds to 118 seconcs.
The assumptions for initial system configuration have enanged for ac-cident modeling (i.e., worst case is when three SGs receive AFW following the break; further, that it is the Afa. ump on the intact loops which is assumed to fail, and that flow from the turbine driven pump delivers 430 gpm to the three intact SGs (rather than 470 g;m to two SGs]).
The FSAR states RCS pressure can be maintained at safety valve setpoint until AFW flow is increased to the intact SGs.
FSAR Table 15.2-1 (Shts 7 and 8) and Figures 15.2-13 through 15.2-26 940 need to be reviewed.
The FSAR has added four Feedwater Bypass Valves (air operated butterfly SRX8/PRPB/46M valves) to the active valve list to assure that they will close for the feedline break.
TV Electric owes a response to NRC letter dated 2/23/88 concerning non-15.3.6
- conservatisms in the e4 del used for ECCS analysis.
The FSAR The SER incorre W y states tnat PCT for Unit 1 is 2001'F.
states that PCT is 2011*F.
Although future FSAR changes are expected as a result of 50.62, no 15.3.9
- changes to Chapter 15 analyses are expected at this time (CPSES t0 use standard Westinghouse ANSAC).
Source terms for primary side equilibrium activities (Table 15.1.4) nave been revised to reflect use of tech spec limits (on RCS activity)
SRX8/PRP8/ 15.4.1 '
-66Wia SFL.6 ano design bases gap activity.
Source terms for secondary side equilibrium activities tTable 15.1-4)
^
have been revised to reflect use of 1 gpm SG tube leak and liqutd and steam phases.
The revised assumptions include the contributions from iodine sp1(ing.
The staff needs to review Taeles 15.1-3 and 15.1-4 V N
'. The FSAR has deleted the realistic analysis for main steam line break.
SRXB/PRP8/ m The FSAR has been revised to include the activity from melted fuel in SRX8/PRP8 15.4.2
- the activity for the red ejection accident, in addition to tne changes A
to primary and secondary source terms creviously cescr10ed.
Staf f needs to reytew Table 15.14 as it appiles to tots accident.
The FSAR has celeted tne realistic analysis case from 'ne roc ejection accident.
The staff neecs to review Table 15.4 4, anich lists parameters and res SRX8/PRP8 for this accident.
W m
s
) Sect. ion 15 (continued) i f
The FSAR has deleted the realistic analysis case from the small 15.4.3
- primary break outside containment accident.
The FSAR has revised the assumption for primary and seconaary source tetes for this accident.
The staff needs to review FSAR Table 15.1-4 as it applies to this accident.
FSAR section 15.6.2 has revised the radiation dose at the EAB for the event involving a Dreak in the 3 in. letdown line located cutsice of the containment.
3RXB/PRPB/15.4.4
- The primary and secondary source term assumptions have eeen
.rg+9. $pt e revised for SGTR.
FSAR Tables 15.1-3, 15.1-4, 15.6-3 and 15.6-4 need to be reviewed (source terms and iodine
- data).
The FSAR has deleted the realistic analysis case from the SGTR accident.
The staff needs to review the SGTR topical reports already submitted.
SRXB/PRP8/ES4fLA The SGTR analysis will be further revised in a future FSAR Amenceent.
+
The assumptions for primary and secondary source term have been SPL8/PRPS 15.4.5
- revised for LOCAs.
The FSAR has revised the numerical values for core and gap isotopic inventories, based on use of design basis gap activity and the use of a three-region core mudel at end of life (FSAR Table 15.6-8).
The FSAR has deleted the realistic analysis case from the LOCA.
analysis (FSAR Table 15.6-9).
The FSAR has deleted mention of TACT-ly, since contractor computer codes were used in the new analysis.
The temperature-vs-time relationship for recirculating water is no longer used.
Leakage from ESF components is conservatively assumed to start 10 minutes after the LOCA and continue for the duration of the ac-cident (FSAR Table 15.6-10).
The FSAR has also deleted the assumption that no credit is taken for radioactive decay.
The FSAR presents the results of the new analysis for ESF leakage.
The afscussion of the gap release case has been deleted.
A high radiation signal from the Control Room air intake monitors will also initiate emergency recirculation and pressurization of the Control Room air conditioning system (in addition to a SIS signal).
The FSAR now assuses a constant breathing rate for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, rather than reducing the rate af ter the first two hours.
The FSAR has reduced the tod' e adsorber efficiency from 100s to 955 lease to the atmosphere of leakage in calculating exposure from
=
from ESF equipment.
The FSAR now specifie* that the differential pressure between the control room and adja unt areas is 0.125 inches water guage (formerlj it only indicated that the pressure was slightly above aretent)
The FSAR analysis for LOCA dose to control roce occupants assumes str train emergency recirculation when, in fact, both trains are actuated by SIS (which results in higher outside air intake) resulting in a decreased thyroid dose and increased whole body and 521ri cases.
Operator action is necessary to test Chapter 15 analysis assumptions (i.e., must turn off one train).
The operating noce sequence was reviseo to comoine several entries anc V
to celete tne period eeycnd 30 cays in considering dose to control SPL3/PRPB room occupants follcwing a LOCA.
O A
. Section 15 15.k.5(continued) 6' SPLB/PRP8 The air vojume in the control room yas 5'.c'lc"I*t'd '-
423,032 ft. rather than 3.219 x 10 ft A
Dose models used to evaluate environmental consequence; of accidents have been revised in Appendix 158.
The analysis of the radiological consequences of containment purging has been deleted from the FSAR, consistent with SRP Section 15.6.5, Appendix C.
For the analysis of the environmental consequences of releases
'.r. ough the containment pressure relief line, reactor coolant iodine con.
centrations and noble gas activity concentrations have been remec tc v
be consistent with proposed tech spec limits.
SPLB/PRPB 15.4.6
- The primary source term assumptions have changed for the waste gas system fatlure accident.
The FSAR has deleted the realistic analysis case (FSAR Table 15.7-1).
15.4.7
The source term assurptions for the radioactive liquid waste systes leak or failure accident have been revised in Table 15.7-3.
The FSAR has deleted the realistic analysis case (Table 15.7-4)
Instead of citing RG 1.4 for the method of calculation Table 15.7-4 now refers to Appendix 158, FSAR Table 15.7-6 has been revised to reflect changes in activity 15.4.8
- released as a result of changes to source term assumptions for the fuel handling accident.
The FSAR has deleted the realistic analysis case (FSAR Table 15.7-7).
The FSAR has deleted the adsorption and filtration efficiencies for inorganic and organic iodine species (since no retention is assumed.)
Instead of citing RG 1.25 for the method of dose calculation and dose conversion assumptions, FSAR Table 15.7-7 now refers to Appendix 158.
FSAR Section 2.4.12 states that controlled release from Squaw Creek 15.4.9
- Reservoir is set by permit from the Texas Department of Water Resources at 1.5 cfs at hwy 144 bridge.
The FSAR gives the storage volume of Squaw Creek Reservoir as 135,062 acre feet (FSAR Section 2.4.12).
The FSAR has revised the source term assumptions anc resulting concentrations for the liquid tank failure accident (FSAR Tables 2.4 20 and 2.4-21).
o e
4' SECTION 22 - TMI-2/ REQUIREMENTS e
!.A.2,3
- This remains an open item from SSER 12 (License Condition (13). system LHF8 I.C.1 functional t*sk analysis).
- The staff needs to review the function and task analysis submitteo by LHF8 letter dated 12/16/85 (TXX-46al).
I.C.5
' Oue to organizational changes within TU, titles anc reporting responsibilities have changed for feedback of operating experience.
I.C.7
- The SER incorrectly states (p. 22-18) that FSAR Section 13.5 describes Westinghouse participation in the development of low power and power ascension test procedures.
- The discussion of Westinghouse Owners' Group efforts needs to be revised (the present discussion is garbled).
- A CROR audit was conducted in 1984 and subsequent major changes have LHF8
!.0.1 been made to the control room. TU may need to conduct environmental surveys and update the FSAR. Another staff audit may be required.
- The staff iteeds to review the function and task analysis submitted by LHFB letter dated 12/16/85 (TXX-4641).
LHFB
' Some open HEDs remain from SSER 6.
- SPOS isolator test program results to be submitted by TU Electric.
LHFB
!.0.2
- TV Electric needs to respond to open items identified in SSER 12.
LHFB
' Appendix 5A to the SER needs to be reviewed (applicability of LHF8 I.G.1 Natural Circulation tests at Diablo Canyon to CPSES).
- Numerous changes have been made to reflect the corrective action pro-PRPB II.B.2 gram.
' The model has been ravised to reflect PASS sources.
PRP8
- The hot cell has been eliminated.
PRP8
- The FSAR has revised the assumptions for some accident analyses, PRPB resulting in changes to the TV Electric response to this THI ttem.
- TV Electric has added relief valves to process sampling systems for ECEB
!!.8.3 overpressure protection per ASME code Section !!!, NC-/155.
- The hot cell has been eliminated.
ECEB
' The staff needs to provide a new SER rewrite to reflect that the PASS ECEB must be demonstrated operable prior to exceeding 55 power.
ECEB
' The staff may need to review procedures.
- The SER indicates that the staff will verify completion cf: (1) traintn; 11.8.4 program before fuel loading; and (2) training of all operational personnel before full power operation.
- New information has been provided in the FSAR on correct safety valve EMEB II.0.1 ring settings.
- The SSER needs to close out this issue based on review of associate correspondence (Txx 4849 dated 6/13/86; TXX 6398 dated a/15/87; TXX 88216 dated 2/12/88.
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. Section 22 (continued)
!!.E.1.1' SER Recossendation GS-4 states that the staff will verify plant pro-SPLB cedures.
- The SER states that the staff should verify acceptability of auxiliary feedwater system test results.
- The response to Reconsnandation GS-7 and GL-5 should be reviewoo in con-Spts junction wtth !!.E.I.2.
-MS.$/C4!1.E.1.2' Staf f needs to review design aspects of this item and provide SER' 1
input.
!!.E.4.1' The SER states that the 48-inch containment purge supply and exhaust valves, will be "sealeo" closed. Clarification of closure requirements should be provided.
!!.E.4.2" This item was listed as Confirmatory Issue 10(j) in SSER 12. The SPL8 staff will have to review applicants' response to close this item (TXX-4644 dated 12/16/85).
i!C8/SRXS !!.F.2
- This item was identified as a license condition (16) in SSER 6.
' Staff needs to review revised program description of this item
- IC8/SRX8 (TXX 88096 dated 1/22/88).
3!CS/SRXS
- The numerical values in Table 22.1 of SSER 6 are not consistent with the FSAR.
- The SSER states that staff must verify that the requirements of
!!.K.1 C.1.5 and C.1.10 for IE Bulletins are satisfied prior to licensing.
SRXS
!!.K.3.5* This item was listed as Confirmatory Issue 10(k) in SSER 12. The staff must review information submitted in response to GL 85-12 on selection and implementation of automatic RCP trip during LOCA (TXX-4904 dated 9/24/86).
SICS II.K.3.9' The staff needs to review an alternate method for disabling the derivative action of the P!0 controller.
!!.K 3.11*Although SSER 6 states that closecut of this item is subject to closure of II.K.3.2, and although !!.K.3.2 was closed out in SSER 6, the SSER write-up didn't specifically close out !!.K.3.11.
!!.K.3.30'The SSER write up needs to reference the NRC SER issued 10/26/87 on the small break LOCA computer code.
!!.K 3.31'The staff needs to review use of the NOTRUMP code.
'SSER 6. Confirmatory item 10(m) incorrectly references 10 CFR 50.56 (the correct reference should be 10 CFR 50.46'
'The response to this TM! Item has been revisec include reference to the destingneuse Owners Group analyses whict generically demonstrate that the previously used WFLASH coot is conservative compared to tne newly approved NOTRUMP coce.
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Section 22 (continued) til.A.1.2'55ER 3, Appendix G ltem 3.H requires onsite post-implementation PEPS review of ERfs.
!!!.0.3.3* Staff needs to review the applicants' new plans for analyzing silver SPLs zeolite cartridges.
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ENCLOSURE 6 SPLB/TU ELECTRIC INFORMATION NEEDS NRC/TU Electric Meeting on September 29, 1988 1.
SER 3.11, lith bullet for the main steamline break outside containment superheat issue which is still open, TV Electric has performed a plant-specific, mass-energy analysis.
7U Electric expected to transmit advance draft FSAR changes to NRC by mid-October, 2.
SER 3.11, 19th bullet Reviseo response to FSAR Question Q140.1 due to be pro,ided with FSAR changes discussed in item 1 above.
3.
SER 6.2.1, 1st bullet TU Electric to research and advise staff who they talked to at NRC and when on interpretation of the broad scope GDC 4 rule amendment as it pertains to subcompartment pressurization as a valid dynamic effect.
4.
SER 3.5.2,1st bullet Staf f requested IU Electric to advise on (or revise FSAR to include) the elevation for which the automobile and the utility pole missiles were analyzed.
5.
SER 3.6.1. 6th bullet Staff requested TV Electric to sjecify in the FSAR that the turbine-driven auxiligry feedwater pump would only be used durino emergency con-ditions and would not be used for normal startups and shutdowns (if the system is to be considered moderate-energy for pipe break purposes during normal operation, i.e., no high-energy pipe break analysis).
6.
SER 9.2.1. 10th bullet TV Electric will advise the staff on which equipment dictates the design basis for the station service water system outlet temperature during an accident and normal shutdown conditions.
7.
SER 9.2.2, no bullet applicable The staff requested TU Electric to check on (1) whether the plant will a.
normally be operated with the levels in the partitioned component cooling water (CCW) surge tank below the equalization opening such that leakage from one side to the other could be detected and (2) whether there are plans to perfnrm periodic che:ks of the integrity of the partition.
b.
TV Electric to advise on whether there are other Significant Deficiency Analysis Reports pursuant to 10 CFR 50.55(e) besides 88-01 that address the seismic category of CCW system piping.
8.
SER 9.2.4, no bullet applicable Item 7 on p. 9.2-41 of ihe F5AR refers to a chemical feed building safety water-hose. TV Electric to check on what this is and report back to staff.
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9.
^SER 9.2.5, no bullet applicable TU Electric to inform the staff about the design basis temperature (s) of equipment actually cooled by the CCW system (reference FSAR p. 9.2-50).
- 10. SER 9.4 TU Eiectric to provide copies of FSAR Sections 9.4A through 9.4E for SPLB's review binders. SSER #4 Appendix H needs to be added te review binders also.
11.
SER 1.6 Staff to consider need to revise FSAR Table 1.3-2 and provide guidance to TV Electric.
- 12. SER 10.4.9. 2nd bullet TU Electric to advise the staff on (1) where the FSAR addresses the ad-dition of safety-related accumulators to steam valves for the turbine-driven auxiliary feedwater pump) w(2) what is the design basis for sizing the accumulators, and (3 hether the accurulators are eeded to hold the valves closed.
- 13. SER 10.4.9. 8th bullet TU Electric needs to clarify FSAR p.10.4-88 at the Amendment 57 change bar on whether one or two motor-driven pumps are necessary for safe pl6nt shutdown.
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- ' " 24 ENCLOSURE 1
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UNITED STATES NUCLEAR REGULATORY COMMISSION
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September 21, 1988 Docktt Nos. 50 445 and 50-446 PEMORANDUM FOR:
Christopher I. Grimes, Director Comanche Peak Project Division Office of Special Projects F9OM:
James H. Wilson, Assistant Director for Prnjects
SUBJECT:
FORTHCOMING MEETING WITH TV ELECTRIC Cate and Time:
Thurshy, September 29, 1988 9:00 am - 4:00 pm location:
One White Flint North 11555 Rockville Pike Dockville, MD 20855 Room No. 10B13
Purpose:
Discussion of FSAR changes under review by the Diant Systems Branch
Participants:
NRC TV Electric J. H. Wilson D. Woodlan M. Malloy M. Patel W. LeFave
' kAd W Jares H. Wi son, Assistant Director for Projects Comanche Peak Project Divisien Office of Special Projects cc:
See rext page
- Meetings between NRC technical staf' and applicants for licenses are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to "Open Meetiros and Statement of NRC Staff Policy," 43 Faderal Register 28058, 6/?8/70.
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W. G. Counsil Comanche Peak Steam Electric Station Texas Utilities Electric Company Units 1 and 2 cc:
Jack R. Newman, Esq.
Asst. Director for Inspec. Programs Newman & Holtzinger, P.C.
Comanche Peak Project Civision Suite 1000 U.S. Nuclear Regulatory Connission 1615 L Street, N.W.
P. 0. Box 1029 Washington, D.C. 20036 Granbury, Texas 76048 Robert A. Wooldridge, Esq.
Regional Administrator, Region IV Worsham, Forsythe, Sampels &
U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 Wooldridge 2001 Bryan Tower, Suite 2:i00 Arlington, Texas 76011 Dallas, Texas 75201 Lanny A. Sinkin Mr. Homer C. Schmidt Christic Institute Director of Nuclear Services 1324 horth Capitol Street Texas Utilities Electric Company Washington, D.C.
20002 Skyway Tower Ms. Billie Pirner Garde. Esq.
400 North Olive Street, L.b. 81 Government Accountability Project Dallas, Texas 75201 Midwest Office Mr. R. W. Ackley 104 East Wisconsin Avenue Appleton, Wisconsin 54911 Stone & Webster Comanche Peak Steam Electric Station David R. Pigott, Esq.
P. O. Box 1002 Glen Rose, Texas 76043 Orrick, Herrington & Sutcliffe 600 Montgomery Street San Francisco, California 94111 Mr. J. L. Vota Westinghouse Electric Corporation Anthony Z. Roisman, Esq.
P. O. Box 355 Pittsburgh, Pennsylvania 15230 Suite 600 1401 New York Avenue, NW Washington, D.C. 20005 Susan M. Toetsen Assistant Attorney General Environtrental Protection Division Robert Jablon P. O. box 12548 Capitol 5tation Bonnie S. Blair Austin, Texas 78711-1548 Spiegel & McDiarmid 1350 hew York Avenue, NW Mrs. Juanita Ellis, President Washington, D.C. 20005-4798 Citizens Association for Souno Energy George A. Parker, Chairman 1426 South Polk Public Utility Connittet 041145. Texas 75224 Ser.ior Citizens Alliance Of Tarrant County, Inc.
Ms. Nancy H. Williams 6048 Wonder Drive CYGNA Energy Services 2121 N. Celifornia Blyc., Suite i.0 Fort Worth, Texas 76133 Walnut Creek, CA 94596
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- h. G. Counsil Comanche Peak Electric Station Texas utilities Electric Company Units 1 and 2 cc:
Joseph F. Fulbright Fulbright & Jaworski 1301 McKinney Street Houston, Texas 77010 Roger D. Walker Manager, Nuclear Licensing Texas utilities Electric Company Skyway Tower 400 North Olive Street, L.B. 91 Dallas, Texas 75201 Texas Utilities Electric Company c/o dethesda Licensing 3 Metro Center, Suite 610 8ethesda, Maryland 20814 William A. Surchette, Esq.
Counsel for Tex-La Electric Cooperative of Texas Heron, Burchette, Ruckert & Rothwell Suite 700 1025 Thomas Jefferson Street, NW Washington, D.C.
20007 GOS ASSOCIATES, thC.
Suite 720 1350 Parkway Place Marietta, Georgia 30067-8237 i
E e
September 21, 1988 Christopher I. Grimes Forthcoming meeting with TU Electric. Thursday, September 29, 1988
Subject:
Discussion of FSAR changes under review by the Plant Systems Rranch DISTRIBUTION Docket File NRC POR Local POR CPPD Reading OSP Deading JPartlow CIGrimes PFMcKee JHWilson JELyons RFWa rnick s
RZaleman 0Crutchfield Wlanning OGC EJordan BGrimes LShao JNorberg AThadani JCraig WLeFave NRC Participants ACRS(10)
GPA/LA JGilliland, RIV/PA Sherry AO:CPPD:0SP JHW1 09/2