ML13322A017
| ML13322A017 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 07/09/1987 |
| From: | SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML13322A014 | List: |
| References | |
| SO23-XVII-4, NUDOCS 8709220494 | |
| Download: ML13322A017 (36) | |
Text
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE S023-XVIT-4 UNITS 2 AND 3 REVISION 2 PAGE 1 OF 36 EFFECTIVE DATlUL 0 9 MT?
STEAM EXTRACTION LINE EROSION MONITORING PROGRAM TABLE OF CONTENTS SECTION PAGE 1.0 OBJECTIVE(S) 2 2.0 REFERENCE(S) 2 3.0 PREREQUISITE(S) 2 4.0 PRECAUTION(S) 3 5.0 CHECKLIST(S) 3 6.0 PROCEDURE(S) 3 6.1 Surveillance Scope 3
6.2 Surveillanc.e Frequency 4
6.3 Surveillance Method 5
6.4 Nondestructive Examinati-on (NDE) 5 6.5 Evaluation of NDE Data Evaluation for Repair or Replacement 6
7.0 RECORD(S) 7 ATTACHMENTS 1
Surveillance Areas 8
2 Surveillance isometric Drawings 11 3
Examination Areas 35 RECEI VED JUL 0 9 1987 RECEIVED CDM CDM SITE JUL 0 9 1987 SITE FILE COPY 0516P QA PROGRAM AFFECTING 8709220494 870918 PDR ADOCK 05000206 G
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE 5023-XVI:-4 UNITS 2 AND 3 REVISION 2 PAGE 2 OF 36 STEAM EXTRACTION LINE EROSION MONITORING PROGRAM 1.0 OBJECTIVE 1.1 This procedure defines the periodic surveillance requirements for monitoring steam line erosion at San Onofre Nuclear Generating Station, Units 2 and 3. The program details those lines, and the locations on the selected lines which are to be inspected, the frequency of the surveillances required, and the criteria for determining if repairs or replacements are required.
2.0 REFERENCES
2.1 Other 2.1.1 Institute of Nuclear Power Operations (INPO) Significant Event Report (SER) 41-82 2.1.2 INPO Significant Operating Experience Report (SOER) 82-11 2.1.3 "Tackling Erosion - Corrosion in Nuclear Steam Generating -Plants," Nuclear Engineering International Magazine, June 1981 2.1.4 Institute of Nuclear Power Operations Significant Operating Experience Report 87-3, dated March 20, 1987.
2.1.5 Electric Power Research Institute Report NP-3944, Erosion/Corros-ion in Nuclear Plant Steam Piping:
Causes and Inspection Program Guidelines, dated April 1985.
3.0 PREREQUISITES 3.1 Prior to use of a user-controlled (pink) copy of this Procedure, it is the user's responsibility to verify that the revision and any TCNs are current by utilizing one of the following methods:
3.1.1 Check it against a.controlled copy and any TCNs; 3.1.2 Access an SCE Document Configuration System (SOCS);
3.1.3 Contact COM by telephone or through counter inquiry; 3.1.4 Obtain a user-controlled (pink) copy of this procedure from CDM; 3.1.5 Reference a current (within one week) Destination Configuration Control Log and associated daily update.
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE S023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 3 OF 36 4.0 PRECAUTIONS 4.1 The person or persons conducting work under this procedure must take the necessary steps to protect themselves from contact with any piping, valves, heaters or other components from which thermal insulation has been removed as severe burns may result.
Should steam or high pressure water leakage be detected, immediately leave the area and notify the Control Room.
5.0 CHECKLIST 5.1 None 6.0 PROCEDURE 6.1 Surveillance Scope 6.1.1 Identification of Lines and Areas to be Inspected
.1 The extraction steam lines to the first, second and fou-rth point heaters-, and the bleed steam line from the first point extraction line to the Moisture Separator Rebeater will be insoected. A total of 106 areas (i.e.,
bends, tees, reducers and areas downstream of control valves, check valves, and flow orifices) per Unit will be tnspected.
The line numbers are listed in
Attachment:
- 1. The points on these lines to be inspected are identified in Attachment 2.
.2 For bends, the entire area of the bend will be inspected.
For tees, an area the length of two pipe diameters on each side of th-e tee will be inspected.
An a-rea three pipe diameters in length will be inspected downstream of reducers, control.alves, check valves, and flow orifices whereever possible.
6.1.2 Ba-sis for Selection
.1 Experience in the erosion surveillance program of several nuclear utilities (Reference 2.1.3) indicates that erosion occurs almost exclusively in the high pressure extraction lines with little or no erosion in the low pressure extraction lines.
.2 In accordance with reference 2.1.4, this program was revised to include additional areas susceptible to erosion corrosion. These areas included downstream of control valves, check valves and flow orifices in accordance with the recommendations of references 2.1.4 and 2.1.5.
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE 5023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 4 OF 36 6.0 PROCEDURE (Continued) 6.1.3 Calculating Erosion Susceptibility
.1 Two calculational methods are used to identify the lines most susceptible to erosion. The first is the correlation between steam velocity and moisture content. The second is the product of pressure, velocity and moisture content (PVX).
For carbon-steel lines with a moisture content greater than 5% and a velocity greater than 150 ft/sec or with a PVX product of greater than 1.0 x 10', erosion can be expected.
.2 The first point extraction lines, the bleed steam lines and the second point extraction lines all have calculated PVX products of over 1.0 x 10' a-nd have moisture contents of over 5% although only the second point extraction lines have a calculated steam velocity of 150 ft/sec.
This, in connection with what was learned from other plants, gives a clear indication that erosion should be expected in these lines.
.3 Experience in other plants has also shown that e-rosion is far more likely to occur at the seco-nd of two consecutive bends than at a single bend following a straight run of pipe.
6.1.4 For the above reasons and the man hours required for inspecting the large number of bends in each line,'not all bends will be surveyed at each inspection interval.
.1 If significant amounts of erosion are seen in the bends innspected, then all remaining bends in the line will be added to the Erosion Survei..la nce-Program.
6.1.5 The fourth point extraction lines have a calculated PVX of under 1.0 x 10' and a moisture content of under 5%,
but have a calculated steam velocity of over 150 ft/sec.
.1 Although no significant erosion may be expected in low pressure extraction lines, and the calculated PVX value is low, two points in each line determined to be the most susceptible to erosion will be inspected. This is due to the high steam velocity (181 ft/sec) and the relatively high moisture content (3.9%).
.2 If any significant erosion is monitored, other bends in the lines will be added to the program.
6.2 Surveillance Frequency Surveillances will be performed every refueling outage for all inspection points. Due to the nonlinearity of erosion rates, additional inspections may be performed between refuelings for areas showing erosion in previous inspections.
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE 5023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 5 OF 36 6.0 PROCEDURE (Continued) 6.2.1 If, after a review of data. it can be determined that no erosion is occurring at some inspection locations, the determination may be made to decrease the frequency of inspection at these points.
6.3 Surveillance Method 6.3.1 Piping wall thickness shall be measured using longitudinal wave ("straight beam") ultrasonic techniques. Digital ultrasonic thickness gauges, calibrated "A-scan" instruments, or the equivalent, may be used.
6.3.2 A rectilinear scan pattern shall be used to examine the entire area of concern, as shown in Attachment 3.
.1 Scanning over circumferential welds should be avoided since grinding of the weld surface would be required in most cases.
.2 Scanning should be performed in such a manner as to identify localized thinning of the wall from the inside surface.
.3 The ultrasonic test report shall record the exact location and actual wall thickness found over the scan area at each inspection paint.
.4 Special rotation shall be made for areas of localized thinning in order to monitor potential further degradation of wall thickness.
6.3.3 Areas where "straight beam" UT indicates wall thinning shall be evaluated using other techniques such as "angl-e beam" UT examination or radiography since the presence of laminar -inclusions in the piping parent material can give spurious indications of erosion.
6.4 Nondestructive Examination (NDE) 6.4'.
Monitoring of steam extraction lines in accordance with this procedure shall be performed using nondestructive examination (NDE) methods and techniques in accordance with procedures which have been approved by a Southern California Edison Level III in the applicable N0E method.
6.4.2 The personnel performing the nondestructive examinattons shall demonstrate their proficiency to the satisfaction of a Southern California Edison Level III.
Surveillance of the work by the Level III is sufficient to satisfy this requirement.
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE S023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 6 OF 36 6.0 PROCEDURE (Continued) 6.4.3 Ultrasonic and/or radiographic examination methods may be used to determine the wall thickness in piping systems at the locations selected.
6.4.4 The Radiographic method shall not be used as the primary examination method for piping having a Nominal Pipe Size greater than 8.
6.5 Evaluation of NDE Data/Evaluation for Repair or Replacement 6.5.1 When an area is identified on a pipe or fitting which is below the minimum wall thickness specified for that size schedule, it shall be subject to engineering evaluation.
6.5.2 The engineering evaluation shall consist of three parts:
(1) determination of the mi-nimum design wall thickness, (2) estimation of the material loss rate and (3) estimation of the remaining service life of the pipe segment or fitting.
6.5.3 The minimum design wall thickness shall be calculated in accordance with the edition and addenda of American National Standard (ANSI) B31.1, Power Piping, appltcable to the installation of the pipe or fitting.
Later editions and/or addenda of ANSI B31.1 may be used.
6.5.4 The material loss rate shall be estimated based on previous examination (thickness measurement) results, or if previous examination results are not available, may be calculated using methods such as those described in reference 2.1.9.
6.5.5 The remaining service life shall be defined as that period of time during which, bas-ed on the material loss rate of 6.5.4, the pipe or fitting shall remain at or above the minimum design wall thickness calculated in 6.5.3, plus 5 percent. The 5 percent factor is a margin of safety added to compensate for.any inaccuracies in the NOE measurements.
6.5.6 The pipe or fitting shall not remain in service beyond its remaining service life as determined in 6.5.5, unless the material loss rate is shown by subsequent examination to be less than originally estimated.
.1 Where the material loss rate is shown by a single subsequent examination to be less than that estimated in 6.5.5, subsequent examinations shall be performed to compensate for inaccuracies in the NDE measurements.
The number and frequency of the subsequent examinations shall be determined on a.case-by-case basis by the engineer cognizant of this program with the concurrence of an SCE Level III in the applicable examination method.
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE S023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 7 OF 36 6.0 PROCEDURE (Continued) 6.5.7 Where the pipe segment is replaced or repaired, 6.2.4, 6.5.6 and 6.5.6.1 above do not apply.
7.0 RECORDS 7.1 Copies of all examination results generated under this procedure shall be maintained in COM for the life of the applicable Unit.
DHenry:0516P
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE 5023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 8 OF 36 ATTACHMENT 1 SURVEILLANCE AREAS Line No.
Description 1301 ML 041 1st Pt. Htr. Extraction Line 1301 ML 042 1st Pt. Htr. Extraction Line 1301 ML 043 2nd Pt. Htr. Extraction Line 1301 ML 044 2nd Pt. Htr. Extraction Line 1301 ML 287 Bleed Steam from the 1st Pt. Htr. Ext. line to MSR E-113 1301 ML 318 1301 ML 319 1301 ML 320 Bleed Steam from 1301ML287 to MSR E-113 101 ML 288 Bleed Steam from the 1st Pt. Htr. Ext. line to MSR E-112 1301 ML 326 1301 ML 327 1301 ML 328 Bleed Steam from 1301ML288 to MSR E-112 1301 ML 095 Connection between cross under piping and 1301 ML 043 1301 ML 104 Connection bet-ween cross under piping anid 1301 ML 044 1301 ML 047 4th Pt. Htr. Extraction Line 1301 ML 048 4th Rt. Htr. Extraction Line ATTACHMENT 1 PAGE 1 OF 3
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE 5023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 9 OF 36 ATTACHMENT 1 Nominal Manufacturers Calculated System 1301 Wall Mini Wall Design tm Line No.
Schedule (inches)
(inches)
(inches) 041-36"-R-KK1
.722
.565
-18"-
40
.562
.492
.314 042-18"-R-KK1 40
.562
.492
.314 287-20"-R-KK1 40
.594
.520
.341
-12"-
40
.406
.355
.240
- 6"-
40
.280
.245
.154 288-12"-R-KK1 40
.406
.355
.240
- 6"-
40
.280
.245
.154 318-6"-R-KK1 40
.2-80
.245
.154 319-6"-R-KK1 40
.280
.245
.154 320- 6"-R-KK1 40
.280
.245
.154 326-6"-R-KKI 40
.280
.245
.154 327-6"-R-KK1 40
.280
.245
.154 328-6"-R-KK1 40
.280
.245
.154 043-24"-R-KK2 Std.
.375
.328
.200
-20"-
Std.
.375
.328
.177 044-24-R-KK2 Std.
.375
.328
.200
-20u-Std.
.375
.328
.177 047-36"-R-LL1 Std.
.375
.328
.084*
048-36"-R-LL1 Std.
.375
.328
.084*
104-20"-R-KK2 Std.
.375
.328
.177 095-20"-R-KK2 Std.
.375
.328
.177
-150 inches will be used for the repair/-replacement criteria to ensure adequate protection against damage from external forces.
ATTACHMENT 1 PAGE 2 OF 3
NUCLEAR GENERATION SITE 0&M SUPPORT PROCEDURE 5023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 10 OF 36 ATTACHMENT 1 Areas for Surveillance The following areas as numbered on the attached marked up isometric drawings (Attachment 2) will be inspected in the Erosion Surveillance Program.
The configuration of these lines are mirror images for Units 2 and 3. For this reason, marked up isometrics for Unit 2 only have been attached. The same areas for Unit 3 will be inspected.
Line No.
Areas 1301 ML 041 - 01, 02, 03, 04, 05, 11, 13, 14, 15, 16 1301 ML 042 - 01, 02, 04, 05, 08, 10, 12, 13, 14 1301 ML 043 -
01, 02, 03. 04,* 07, 10, 11, 13, 14, 15 1301 ML 044 - 01, 02, 03, 05, 07, 08, 11, 12, 14. 15 1301 ML 287 -
01, 03, 04, 05, 09, 11, 13, 14, 15, 1-, 18, 20, 21, 22, 23, 24, 25
.1301 ML 318 -
02, 04, 05 1301 ML 319 - 02, 01, 04 1301 ML 320 - 02, 01, 04 1301 ML 288 - 01, 02, 04, 09, 11, 13, 14, 15, 16, 18, 20, 21, 22, 23, 24, 25 1301 ML 326 - 02, 05, 06 1301 ML 327 - 02, 01, 04 1301 ML 328 - 02, 01, 04 1301 ML 095 -
01, 02, 03 1301 ML 104 - 01, 02, 03 1301 ML 047 - 03, 02, 07, 08 1301 ML 048 --03, 02, 07, 08 This inspection point is shown on the extension of line 043 found on 1301 ML 095 (page 30 of 35).
ATTACHMENT 1 PAGE 3 OF 3
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE 5023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 11 OF 36 ATTACHMENT 2 HP TURBINE K-001, SYS 1301 1 ST POINT HEATER E-037 SYS 1301 S2-1301-ML-041-36-R-KKI 4'
041-01 0-4
.04104 San AV141t Co 7-7-S AtTHET2PGo F2
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE S023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 12 OF 36 ATTACHMENT 2 HP TURBINE K-001, SYS 1301 1 ST POINT HEATER E-037 SYS 1301 S2-1301-(ST)-041-18"-R-KKI- (32C*)
05 o
Bes AvJAILAtB-E Coed
(
E 01-107 0
ATTACHMENT 2 PAGE 2 OF 24
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE S023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 13 OF 36 ATTACHMENT 2 LINE 041 HP TURBINE K001, SYS 1301 1 ST POINT HEAT(S) E-036 SYS 1301 S2-1301-(ST)-ML-042-18"-R-KK1 (32C*)
~~o 042-03 o.
042-04 d042-06020
-Ees-AVAiLAsLL CoP'j 1 1 ATTACHMENT 2 PAGE 3 OF 24
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE S023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 14 OF 36 ATTACHMENT 2 LINE 041 HP TURBINE K001, SYS 1301 1 ST POINT HEAT(S) E-036 SYS 1301 52-1301-(ST)-ML-042-18"-R-KK1- (32C*)
1000 042-09 ATTACHMENT 2 PAGE 4 OF 24
NUCLEAR GENERATION SITE J&M SUPPORT PROCEDURE S023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 15 OF 36 ATTACHMENT 2 COLD REHEAT STEAM HDRS, SYS 1301 2ND POINT HEATER E038 SYS 1301 S2-1301-ML-043-20"-R-KK2 f~0*
043-02 043-03 ATTACHMENT 2 PAGE 5 OF 24
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE S023-XVil-4 UNITS 2 ANO 3 REVISION 2 PAGE 16 OF 36 ATTACHMENT 2 COLD REHEAT STEAM HORS, SYS 1301 2ND POINT HEATER E038 SYS 1301 S2-1301-ML-043-20"-R-KK2 1P 3-2-0.
043 3.043 le 4-.O-43 o0 043-09.
43-10 ATTACHMENT 2 PAGE 6 OF 24
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE 5023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 17 OF 36 ATTACHMENT 2 COLD REHEAT STEAM HDRS, SYS 1301 2ND POINT HEATER E039 SYS 1301 52-1301-ML-044-20"-R-KK2 OKs
-00
.00, 044 -02 044 -060 044 -07 044-07 A C N 2 "4
be TAq.
ATTACHMENT 2 PAGE 7 OF 24
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE 5023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 18 OF 36 ATTACHMENT 2 COLD REHEAT STEAM HORS, SYS 1301 2ND POINT HEATER E039 SYS 1301 52-1301-ML-044-20"-R-KK2
.044-0 044 -13 *4 10
..044 -12 044 -'10 O
- 44.
/ET 2
A AE CCP/
ATTACHMENT 2 PAGE 8 OF 24
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE 5023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 19 OF 36 ATTACHMENT 2 LINE 041 M/S SUP HDR TURBINE K001, SYS 1301 MOISTURE SEPARATOR (W) E113 SYS 1301 52-1301-(ST)-ML-287-12"-R-KK1 (32C*)
A st 287-01 0287-05
.A oof 287-07 ATTACHMENT 2 PAGE 9 OF 24
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE S023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 20 OF 36 ATTACHMENT 2 LINE 041 M/S SUP HOR TURBINE KOOl, SYS 1301 MOISTURE SEPARATOR W HEAT E113 SYS 1301 S2-1301-ML-287-12"-R-KK1 287-14
-287 -12 1Z87-t1 ATCMN 287-10 287-09 a
287-2 4 as Po 287 -23 287-22 287 -08 ATTACHMENT 2 PAGE 10 OF 24
NUCLEAR GENERATION SITE O&M SuPPORT PROCEDURE S023-XViI-4 UNITS 2 AND 3 REVISION 2 PAGE 21 OF 36 ATTACHMENT 2 LINE 041 M/S SUP HOR TURBINE K001. SYS 1301 MOISTURE SEPARATOR W HEAT E113 SYS 1301 S2-1301-ML-287-6"-R-KK1 2287 287-18 287-17 2-287-2 7-7-27 ATTACHMENT 2 PAGE 11 OF 24
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE S023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 22 OF 36 ATTACHMENT 2 LINE 287 BLED STEAM TURBINE K001, SYS 1301 MOISTURE SEPARATOR HEAT E113 SYS 1301 52-1301-ML-318-6"-R-KK1 318-04 318-05 c
7 N 318-01 o
I*
3A8 - O PLooRfL.rTo*
T A 'AILA LE CC,/
AN 27 1 7 ATTACHMENT 2 PAGE 12 OF 24
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE S023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 23 OF 36 ATTACHMENT 2 LINE 287 BLED STEAM TURBINE K001, SYS 1301 MOISTURE SEPARATOR E113 SYS 1301 S2-1301-ML-319-6"-R-KK1
£ Mom tuar iowro r
3119-03 QTtoa s
319-04 uo/.c.
a.319
-02 349 - 01' L-ST Au18u~t CoPY 7
?7 ATTACHMENT 2 PAGE 13 OF 24
NUCLEAR GENERATION SITE D&M SUPPORT PROCEDURE S023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 24 OF 36 ATTACHMENT 2 LINE 287 BLED STEAM TURBINE KOOl, SYS 1301 MOISTURE SEPARATOR HEAT E113 SYS 1301 52-1301-ML-320-6"-R-KK1 MOJWrt/
JCPARATOE I RZWZArCR rll
~4 320 -03 IZ~r-Jro-47 14?
ATTACHMENT 2 PAGE 14 OF 24
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE S023-XV1l-4 UNITS 2 AND 3 REVISION 2 PAGE 25 OF 36 ATTACHMENT 2 LINE 287 M/S SUP HOR TURBINE K001, SYS 1301 MOISTURE SEPARATOR (E) HEAT E113 SYS 1301 S2-1301 (ST)-ML-288-12"-R-KK1 (32C-)
288-07 288-22 0A 2o 88 -03 288-02 AAM 2
PPGLELC OF 24 ATTACHMENT 2 PAGE 15 OF 24
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE S023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 26 OF 36 ATTACHMENT 2 LINE 287 M/S SUP HDR TURBINE KOOl, SYS 1301 MOISTURE SEPARATOR E HEAT E113 SYS 1301 S2-1301-ML-288-12"-R-KK1 288 -15 m
0
.288 -14 SPa28 1
288 -13 28 8 -10 2B8-09..
o, 288-08 82a-t-54*t
-- - 23 ATTMET 2AGLE CO/
0 ATTACHMENT 2 PAGE 16 OF 24
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE S023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 27 OF 36 ATTACHMENT 2 LINE 287 M/S SUP HDR TURBINE K001, SYS 1301 MOISTURE SEPARATOR E HEAT E112 SYS 1301 S2-1301-ML-288-6"-R-KK1
.s).
aL /
- r-r mr S
88-21 288-17 2 20 esi *L Mr 288 -19
.a BEST hAJA LP&C COcY AT N 2A 7-7 F7 0
ATTACHMENT 2 PAGE 17 OF 24
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE S023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 28 OF 36 ATTACHMENT 2 LINE 288 HP TURBINE K001, SYS 1301 MOISTURE SEPARATOR HEAT E112 SYS 1301 S-2-1301-ML-326-6"-R-KK1 326 -04 s326
-02 3230-03 EeST A VA ILA LE COPY 7-7-87 ATTACHMENT 2 PAGE 18 OF 24
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE S023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 29 OF 36 ATTACHMENT 2 LINE 288 HP TURBINE K001, SYS 1301 MOISTURE SEPARATOR HEAT E112 SYS 1301 S2-1301-ML-327-6"-R-KK1 Nee
.&, e 37-02 327-01 327-o0 327-03 orf BesT AVILABLE CCPe 7 7 ATTACHMENT 2 PAGE 19 OF 24
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE S023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 30 OF 36 ATTACHMENT 2 LINE 288 HP TURBINE K001 SYS 1301 MOISTURE SEPARATOR HEAT E112 SYS 1301 52-1301-ML-328-6"-R-KK1 328-01 02 328--03 ATTACHMENT 2 PAGE 20 OF 24
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE 5023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 31 OF 36 ATTACHMENT 2 COLD REHEAT STEAM LINE (W) SYS 1301 LINE 043 SYS 1301 S2-1301-ML-095-20"-R-KK2
-K..
095-p3 095-02 o
1 095-04 4'
043-05 04T-06 ATTACHMENT 2 PAGE 21 OF 24
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE S023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 32 OF 36 ATTACHMENT 2 COLD REHEAT STEAM HORS SYS 1301 LINE 044 SYS 1301 52-1301-ML-104-20"-R-KK2 04-01 10404*02 7 e 7 ATTACHMENT 2 PAGE 22 OF 24
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE SU23-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 33 OF 36 ATTACHMENT 2 EXTRACTION STEAM IN CONDENSER NECK LINE 5-2-1301-ML-047 047-0Vt 4%t 047-05 7-4
~
.47-03 ATTACHMENT 2 PAGE 23 OF 24
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE S023-XVII-4 UNITS 2 ANO 3 REVISION 2 PAGE 34 OF 36 ATTACHMENT 2 EXTRACTION STEAM IN CONDENSER NECK LINE S-2-1301-ML-048 Q
OV.
048
-~9 oo
-01 7-7-87 ATTACHMENT 2 PAGE 24 OF 24
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE 5023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 35 OF 36 ATTACHMENT 3 EXAMINATION AREAS INSPECTION POINT "A" (FLANGED END VALVE)
VALYK FLAMG WE= XFS HN FLM 1113 U.T. Scan AR INSPECTION POINT "A" (WELD END VALVE)
FMS FM5 OR REWCRL INSPECTION POINT "B" (CAPPED TEE OR LATERAL)
- U.T. SCAN ARZA U.T. SCAM
.A NP 1
ATT ACHMENT 3 PAE1 O
NUCLEAR GENERATION SITE O&M SUPPORT PROCEDURE S023-XVII-4 UNITS 2 AND 3 REVISION 2 PAGE 36 OF 36 ATTACHMENT 3 EXAMINATION AREAS Pinzl (oWSno H
?IFE 0R REU INSPECTION POINT "C 0
APPOX. 750 U.T 0.T.
OFEI10M SCAN AREA U.T. SCAN U.S. SCAN A
SECT A*A INSPECTION POINT "B" (STANDARD ELBOW) 0516P ATTACHMENT 3 PAGE 2 OF 2