ML20198G400
| ML20198G400 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 12/22/1998 |
| From: | SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML20138M341 | List: |
| References | |
| NUDOCS 9812290071 | |
| Download: ML20198G400 (32) | |
Text
--
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) e.
Inspection Frequency
)
The above required inservice inspections of the non-repaired SG l
tubes shall be performed at the following frequencies:
1.
The first inservice inspection shall be performed after 6 effective full power months but within 24 calendar months of initial critically. _ Subsequent inservice inspections shall be performed at intervals of not less i
than 12 nor more than 24 calendar months after the previous inspection.
If two consecutive inspections, not j
including the preservice inspection, result in all inspections results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months; i
2.
If the results of the inservice inspection of a SG conducted in accordance with Table 5.5.2.11-1 at 40-month intervals fall in Category C-3, the inspection shall be increased to at least once per 20 months.
The increase in j
inspection frequency shall apply until the subsequent inspections satisfy the criteria of Specification i
5.5.2.11.e.1, the interval may then be extended to a l
maximum of once per 40 months; and 3.
Additional, unscheduled inservice inspections shall be performed on each SG in accordance with the first sample inspection specified in Table 5.5.2.11-1 during the shutdown subsequent to any of the following conditions:
4 a)
Primary-to-secondary tubes leak (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Technical Specification 3.4.13, or b)
A seismic occurrence greater than the Operating Basis Earthquake, or 1
c)
A loss-of-coolant accident requiring actuation of the Engineered Safety Features, or i
d)
A main steam line or feedwater line break.
(continued)
SAN ON0FRE--UNIT 2 5.0-16 Amendment No. 4W 140 8/26/98 i
~
9912290071 981222 PDR ADOCK 05000361 P
T-,
r Procedures, Programs, and Manuals 5.5 1
5.5 Procedures, Programs, and Manuals (continued) i 5.5.2.11 Steam Generator (SG) Tube Surveillance Progran (continued) s j)
Tube Repair - refers to a process that reestablishes tube serviceability. Acceptable tube repairs will _be performed by the following process:
1 TIG welded sleeving as described in ABB/CE Topical
)
Report, CEN-630-P, Rev. 2, is currently approved by
]
the NRC.
l Tube repair includes the installation by welding of the sleeves, heat treatment in accordance with CEN-a i
630-P, Rev. 2, to remove the stresses that are i
introduced by the sleeve installation, acceptance testing of the sleeve, and nondestructive examination for future comparison. Tube repair can be performed a
on certain tubes that have been previously plugged as 4
j a corrective or preventive measure. A tube inspection of the full length of the tube shall be performed on a previously plugaed tube prior to returning the tube to_ service.
i 2.
The SG shall be determined OPERABLE af ter completing the corresponding actions (plug or repair all tubes exceeding the repair limit and all tubes containing through-wall cracks, and plug all sleeved tubes that exceed the repair i
criteria) required by Tables 5.5.2.11-1 and 5.5.2.11-2.
g.
Reports i
The content and frequency of written reports shall be in i
accordance with Technical Specification 5.7.2, "Special Reports."
i 4
i.
3 1
1
~
l i
j (continued) i SAN ON0FRE--UNIT 2 5.0-19 Amendment No. W 140 8/26/98 i
. - _.. ~ _
a Procedures, Programs, and Manuals 5.5 a
i 5.5 Procedures, Programs, and Manuals (continued)
J
]
TABLE 5.5.2.11-1 (page 1 of 1) l 1
STEAM GENERATOR TUBE INSPECTION SUPPLEMENTAL SAMPLING REQUIREMENTS i
1st Sample Inspection 2nd Sample Inspection 3rd Sample Inspection
)
l Action Action Action j
Sample Size Result Required Result Required Result Required i
1 A ninimum of C.1 None N/A N/A N/A N/A 5 tubes per SG C-2 Plug or repair C-1 None N/A N/A 1
by sleeving defective tubes Plug or repair by N/A N/A
}
and inspect an sleeving defective j
additional 255 tubes and C-1 N/A l
tubes in this inspection an SG.
additional 45 C-2 Plug or repair l
tubes in this SG.
by sleeving defective j
tubes.
l C-3 Perform action for C-3 result of first sample.
C-3 Perform N/A N/A j
action for
?
C-3 result of e
first sample.
C-3 Inspect all All other SGs None N/A N/A tubes in this C-1 l
l SG, plug or i
repair by sleeving Some SGs C-2 Perform N/A N/A j
defective tubes but no other action for j
and inspect 25 is C-3 C-2 result of l
2 tubes in each second other SG.
sample.
I Notification to NRC Additional SG Inspect all tubes i
pursuant to is C-3 in each SG and N/A N/A 10CFR50.72 plug or repair by sleeving defective tubes.
]f Notification to
)
NRC pursuant to j
j S = 3 N/n % Wherg N is the number of SGs in the unit and n is the number of t
SGs inspected during inspection period.
,i 1
(continued)
SAN ONOFRE--UNIT 2 5.0-19a Amendment No. +B7 140 8/26/98 i
4
.m
- + - -
r.
PCN-489 ATTACHMENT B EXISTING TECHNICAL SPLCIFICATIONS SAN ON0FRE UNIT 3 4
i
-~
4 9
4 3
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2,11 Steam Generator (SG) Tube Surveillance Program (continued) e.
Inspection Frequency 1
The above required inservice inspections of the non-repaired SG l
tubes shall be performed at the following frequencies:
s i
1.
The first inservice inspection shall be performed after 6 effective full power months but within 24 calendar months of initial critically. Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection.
If two consecutive inspections, not 1
including the preservice inspection, result in all inspections results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional i
degradation has occurred the inspection interval may be extended to a maximum of once per 40 months; 2.
If the results of the inservice inspection of a SG j
conducted in accordance with Table 5.5.2.11-1 at 40-month intervals fall in Category C-3, the inspection shall be increased to at least once per 20 months.
The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of Specification 5.5.2.11.e.1, the intercal may then be extended to a l
maximum of once per 40 months; and 3.
Additional, unscheduied inservice inspections shall be performed on each SG in accordance with the first sample inspection specified in Table 5.5.2.11-1 during the shutdown subsequent to any of the following conditions:
i a)
Primary-to-secondary tubes leak (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Technical Specification 3.4.13, or b)
A seismic occurrence greater than the Operating Basis Earthquake, or c)
A loss-of-coolant accident requiring actuation of the Engineered Safety Features, or d)
A main steam line or feedwater line break.
(continued)
SAN ONOFRE--UNIT 3 5.0-16 Amendment No. 1461328/26/98
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) j)- Tube Repair - refers to a process that reestablishes tube serviceability. Acceptable tube repairs will be performed by the following process:
TIG welded sleeving as described in ABB/CE Topical Report, CEN-630-P, Rev. 2, is currently approved by the NRC.
Tube repair includes the installation by welding of the sleeves, heat treatment in accordance with CEN-630-P, Rev. 2, to remove the stresses that are introduced by the sleeve installation, acceptance testing of the sleeve, and nondestructive examination for future comparison. Tube repair can be performed on certain tubes that have been previously plugged as a corrective or preventive measure. A tube inspection of the full length of the tube shall be performed on a previously plugged tube prior to i
returning the tube to service.
1 2.
The SG shall be determined OPERABLE after completing the corresponding actions (plug or repair all tubes exceeding the repair limit and all tubes containing through-wall cracks, and plug all sleeved tubes that exceed the repair criteria) required by Tables 5.5.2.11-1 and 5.5.2.11-2.
g.
Reports e
The content and frequency of written reports shall be in i
accordance with Technical Specification 5.7.2, "Special Reports."
(
i.
i 1
i t
l (continued)
SAN ON0FRE--UNIT 3 5.0-19 AmendmentNo.+161328/26/98
+,
...-,-,-,m v-,-
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.11 Steam Generator Tube Surveillance Program TABLE 5.5.2.11-1 (page 1 of 1) l STEAM GENERATOR TUBE INSPECTION SUPPLEMENTAL SAMPLING REQUIREMENTS ist Sample Inspection 2nd Sample Inspection 3rd sample Inspection l
Action Action Action Sample $1re Reseit Required Result Required Result Required A minimum of C-1 None k/A N/A N/A N/A 5 tubes per SG C?
Plug or repair C-1 None N/A N/A l
Dy sleeving defective tubes Plug or repair by N/A N/A and inspect an sleeving additional 25 defective tubes C-1 N/A tubes in this and inspection an SG.
additional 45 C-2 Plug or repair tubes in this $G.
by sleeving defective tubes.
C-3 Perform action for C-3 result of first sample.
C-3 Perform N/A N/A
)
action for i
C-3 result of first sample.
C-3 Inspect all All other SGs None N/A N/A tubes in this C-1 SG, plug or repair by sleeving Some SGs C-2 Perform N/A N/A defective tubes but no other action for and inspect 25 is C-3 C-2 result of tubes in each second other SG.
sample.
Notification to NRC Additional SG Inspect all tubes 4
pursuant to is C-3 in each $G and N/A N/A 10CFR50.72 plug or repair by sleeving defective tubes.
j Notification to NRC pursuant to 10CFR50.72.
S = 3 N/n % Where N is the number of SGs in the unit and n is the number of SGs inspected during inspection period.
(continued)
SAN ON0FRE--UNIT 3 5.0-19a Amendment No. H 6 132 8/26/98
1
~
PCN-489 i
l l
l 1
Attachment C PROPOSED TECHNICAL SPECIFICATIONS (Strike out for deletions and highlight for additions.)
SAN ONOFRE UNIT 2 i
t j
l i
l b.
4 4
d
+
i i
I
.= _-
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) e.
Inspection Frequency The above required inservice inspections of the non-repaired SG tubes.shall be performed at the following frequencies:
l 1.
The first inservice inspection shall be performed after 6 1
effective full power months but within 24 calendar months of initial criticalitycritically.
Subsequent l
1 inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection.
If two consecutive inspections, not including the preservice inspection, result in all inspections results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per.40 months; 2.
If the results of the inservice inspection of a SG conducted in accordance with Table 5.5.2.11-1 at 40-month intervals fall in Category C-3, the inspection shall be increased to at least once per 20 months.
The increase in inspection frequercy shall apply until the subsequent inspections satisfy the criteria of Specification 5.5.2.11.e.1, the interval may then be extended to a maximum of once per 40 months; and 3.
Additional, unscheduled inservice inspections shall be performed on each SG in accordance with the first sample 4
inspection specified in Table 5.5.2.11-1 during the shutdown subsequent to any of the following conditions:
a)
Primary-to-secondary tubes ieak (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Technical Specification 3.4.13, or l
b)
A seismic occurrence greater than the Operating Basis l
Earthquake, or I
c)
A loss-of-coolant accident requiring actuation of the Engineered Safety Features, or d)
A main steam line or feedwater line break.
)
(continued)
SAN ON0FRE--UNIT 2 5.0-16 Amendment No. W 140 m
m
- + - -
.a w
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) j)
Tube Repair - refers to a process that reestablishes tube serviceability. Acceptable tu.be repairs will be performed by the following processes.
l i)
TIG welded sleeving as described in ABB/CE l
Topical Report, CEN-630_P, Rev. 2, is currently approved by the NRC i and/or
~
11)
L'asehweidid i51eeving {as" described in the NRC approved Westinghouse" Topical; Reports.WCAP-13698 Rev.' 2,'WCAP-13698:Rev.-2 Addendum 1, and WCAP 15014( ~
~
Tube repair includes the installation by welding of-the sleeves, heat treatment in accordance with CEN-630-P, Rev. 2, arid /orlWCAP-13698,L. Revs;2fto remove l
the stresses that are introduced by the sleeve installation, acceptance testing of the sleeve, and nondestructive examination for future comparison.
Tube repair can be performed on certain tubes that have been previously plugged as a corrective or preventive measure. A tube inspection of the full length of the tube shall be performed on a previously plugged tube prior to returning the tube to service.
2.
The SG shall be determined OPERABLE after completing the corresponding actions (plug or repair all tubes exceeding the repair limit and all tubes containing through-wall cracks, and plug all sleeved tubes that exceed the repair criteria) required by Tables 5.5.2.11-1 and 5.5.2.11-2.
l g.
Reports l
The content and frequency of written reports shall be in j
accordance with Technical Specification 5.7.2, "Special Reports."
l 4
f l
(continued)
SAN ON0FRE--UNIT 2 5.0-19 Amendment No. 4 W 140 i
l l
l ~
L Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued)
TABLE 5.5.2.11-1 (page 1 of 1)
STEAM GENERATOR TUBE INSPECTION SUPPLEMENTAL SAMPLING REQUIREMENTS i
i 1st Sample Inspection 2nd Sample Inspection 3rd Sample Inspection l
Action Action Action 5
Sample Sire Result Required Result Required Result Required 3
i A minimum of C-1 None N/A N/A N/A N/A
$ tubes per i
SG C-2 Plug or repair C-1 None N/A N/A by sleeving defective tubes Plug or repair by 9
l 4
1 and inspect an sleeving defective addittonal 25 tubes and C-1 fr/ANone l
tubes in this inspect an
~
l
$G.
additional 45 C2 Plug or repair i
tubes in this $G.
by sleeving defective tubes.
li j
C-3 Perform i
f action for 5
C-3 result of first sample.
C-3 Perform N/A N/A i
{!
action for C-3 result of li first sample, C-3 Inspect all All other SGs None N/A N/A i
tubes in this C-1 1
SG, plug or j
repair by sleeving Some SGs C 2 Perform N/A N/A defective tubes but no other action for and inspect 25 is C-3 C-2 result of 4
tubes in each second 2
other $G.
sample.
Notification i
to NRC Additional SG Inspect all tubes j
pursuant to is C-3 in each SG and N/A N/A j
10CFR50.72 plug or repair by sleeving 2
i defective tubes.
Notification to NRC pursuant to 10CFR50.72.
1 4
S=3N/n%WhereNisthenumber,0fSGsintheunitandnisthenumberof 1
SGs inspected during inspection period.
2 (continued)
SAN ON0FRE--UNIT 2 5.0-19a Amendment No. +27 140
I
~
FCN-489 l
1 l
Attachment D PROPOSED TECHNICAL SPECIFICATIONS (Strike out for deletions and highlight for additions.)
i SAN ONOFRE UNIT 3 i
4 s
?
f.
1
,,,--o m
Procedures, Programs, and Manuals-i 5.5 5.5 Procedures, Programs, and Manuals (continued) i 5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) e.
Inspection Frequency i
The above required inservice inspections of the non-repaired SG tubes shall be performed at the following frequencies:
A 1.
The first inservice inspection shall be perforr..ed arte.
effective full power months but within 24 calendar months of initial criticalitycritically. Subsequent l
inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months af ter the previous inspection.
If two consecutive inspections, not including the preservice inspection, result in all inspections results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months; 2.
If the results of the inservice inspection of a SG conducted in accordance with Table 5.5.2.11-1 at 40-month intervals fall in Category C-3, the inspection shall be increased to at least once per 20 months. The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of Specification 5.5.2.11.e.1, the interval may then be extended to a maximum of once per 40 months; and 3.
Additional, unscheduled inservice inspections shall be performed on each SG in accordance with the first sample inspection specified in Table 5.5.2.11-1 during the shutdown subsequent to any of the following conditions:
a)
Primary-to-secondary tubes leak (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Technical Specification 3.4.13, or b)
A seismic occurrence greater than the Operating Basis Earthquake, or c)
A loss-of-coolant accident requiring actuation of the Engineered Safety Features, or d)
A main steam line or feedwater line break.
(continued)
SAN ON0FRE--UNIT 3 5.0-16 Amendment No. H6 132
i Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) j)
Tube Repair - refers to a process that reestablishes tube serviceability. Acceptable tube repairi will be performed by the following processes:
l i)
TIG welded sleeving as described in ABB/CE l
Topical Report, CEN-630-P, Rev. 2, is currently approvedbytheNRCrand/or L' 5eEwelded7sleev'iriglasidescrib'ed !inTthe?NRC.
~
ii) a approved Westinghouse 1 Topical: Reports WCAP "~
Rev22,~WCAP-1369.8 Rev( 2: Addendum 1, Land',-
3 WCAP-15014.
Tube repair includes the installation by welding of the sleeves, heat treatment in accordance with CEN-630-P, Rev. 2, and/oLWC.AP-13698,tRevd2 to remove l
the stresses that are introduced by the sleeve installation, acceptance test'ing of the sleeve, and nondestructive examination for future comparison.
Tube repair can be performed on certain tubes that have been previously plugged as a corrective or preventive measure. A tube inspection of the full length of the tube shall be performed on a previously plugged tube prior to returnirg the tube to service.
2.
The SG shall be determined OPERABLE after completing the corresponding actions (plug or repair all tubes exceeding the repair limit and all tubes containing through-wall cracks, and plug all sleeved tubes that excaed the repair criteria) required by Tables 5.5.2.11-1 and 5.5.2.11-2.
9 Reports The content and frequency of written reports shall be in accordance with Technical Specification 5.7.2, "Special Reports."
(continued).
SAN ON0FRE--UNIT 3 5.0-19 Amendment No. 1-16 132 i
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.11 Steam Generator Iube Surveillance Program TABLE 5.5.2.11-1 (page 1 of 1)
STEAM GENERATOR TUBE INSPECTION SUPPLEMENTAL SAMPLING REQUIREMENTS 1st $ ample Inspection 2nd Sample Inspection 3rd Sample Inspection Action Action Action Sample $1re Result Required Result Required Result Required A minimum of C.1 None N/A N/A N/A N/A
$ tubes per SG C-2 Plug or repair C-1 None N/A N/A by sleeving defective tubes Plug or repair by
- fA 4/A l
and inspect an sleeving additional 25 defective tubes C-1
- fANone l
tubes in this and Inspect an
$G.
additional 45 C2 Plug or repair tubes in this $G.
by sleeving defective tubes.
~
C-3 Ferform action for C-3 result of first sample.
C-3 Perform N/A N/A action for C.3 result of first sample.
C.3 Inspect all All other SGs None N/A N/A tubes in this C-1 SG, plug or repair by sleeving Some $Gs C-2 Perform N/A N/A defective tubes but no other action for and inspect 25 is C-3 C-2 result of 1
tubes in each second other $G.
sample.
Notification to NRC Additional SG Inspect all tubes pursuant to is C.3 in each SG and N/A N/A 10CFR50.72 plug or repair by sleeving 4 -
defective tubes.
Notification to NRC pursuant to 10CFR50.72.
5 = 3 N/n % Where N is the number of SGs in the unit and n is the number of SGs inspected during inspection period.
l (continued) d SAN ON0FRE--UNIT 3 5.0-19a Amendment No. 4% 132
PCN-489 Attachment E PROPOSED TECHNICAL SPECIFICATIONS (Changesincorporated)
SAN ON0FRE UNIT 2 l
f 4
1 i
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) e.
Inspection frequency The above required inservice inspections of the non-repaired SG tubes shall be performed at the following frequencies:
1.
The first inservice inspection shall be performed after 6 effective full power months but within 24 calendar months of initial criticality.
Subsequent inservice l
inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months af ter the previous inspection.
If two consecutive inspections, not including the preservice inspection, result in all inspections results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per.40 months; 2.
If the results of the inservice inspection of a SG conducted in accordance with Table 5.5.2.11-1 at 40-month intervals fall in Category C-3, the inspection shall be increased to at least once per 20 months.
The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of Specification 5.5.2.11.e.1, the interval may then be extended to a maximum of once per 40 months; and 3.
Additional, unscheduled inservice inspections shall be performed on each SG in accordance with the first sample inspection specified in Table 5.5.2.11-1 during the shutdown subsequent to any of the following conditions:
a)
Primary-to-secondary tubes leak (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Technical Specification 3.4.13, or b)
A seismic occurreace greater than the Operating Basis Earthquake, or c)
A loss-of-coolant accident requiring actuation of the Engineered Safety Features, or d)
A main steam line or feedwater line break.
(continued)
SAN ON0FRE--UNIT 2 5.0-16 Amendment No.
F
~
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) l 5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) j)
Tube Repair - refers to a process that reestablishes j
tube serviceability. Acceptable tube repairs will be i
performed by the following process:
l i
i)
TIG welded sleeving as described in ABB/CE l
l Topical Report, CEN-630-P, Rev. 2, is currently approvedbytheNRC,and/or J
l ii)
Laser welded sleeving as described in the NRC approved Westinghouse Topical Reports WCAP-13698 4
Rev. 2, WCAP-13698 Rev. 2 Addendum 1, and l
i Tube repair includes the installation by welding of i
the sleeves, heat treatment in accordance with CEN-630-P, Rev. 2, and/or WCAP-13698, Rev. 2 to remove l
i the stresses that are introduced by the sleeve i
installation, acceptance testing of the sleeve, and l
nondestructive examination for future comparison.
{
Tube repair can be performed on certain tubes that have been previously plugged as a corrective or preventive measure. A tube inspection of the full length of the tube shall be performed on a previously plugged tube prior to returning the tube to service.
2.
The SG shall be determined OPERABLE after completing the i
corresponding actions (plug or repair all tubes exceeding the repair limit and all tubes containing through-wall cracks, and plug all sleeved tubes that exceed the repair criteria) required by Tables 5.5.2.11-1 and 5.5.2.11-2.
g.
Reports The content and frequency of written reports shall be in accordance with Technical Specification 5.7.2, "Special Reports."
(continued)
SAN ON0FRE--UNIT 2 5.0-19 Amendment No.
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued)
TABLE 5.5.2.11-1 (page 1 of 1)
STEAM GENERATOR TUBE INSPECTION SUPPLEMENTAL SAMPLING REQUIREMENTS lst Sample Inspection 2nd Sample Irspection 3rd Sample Inspection Action Action Action Sample Size Result Required Result Required Result Required A minimum of C-1 None N/A N/A N/A N/A 5 tubes per SG C-2 Plug or repair C-1 None N/A N/A by sleeving defective tubes Plug or repair by l
and inspect an sleeving defective l
additional 25 tubes and C-1 None tubes in this inspect an SG.
additional 45 C-2 Plug or repair tubes in this SG.
by sleeving defective tubes.
C-3 Perform action for C-3 result of first sample.
C-3 Perform N/A N/A action for C-3 result of first sample.
C-3 Inspect all All other SGs None N/A N/A tutes in this C-1 SG. plug or repair by sleeving Some SGs C-2 Perform N/A N/A defective tubes but no other action for and inspect 25 is C-3 C-2 result of tubes in each second other $G.
sample.
Notification i
to NRC Additional SG Inspect all tubes pursuant to is C-3 in each SG and N/A N/A 10CFR50.72 plug or repair by i
sleeving defective tubes.
]
Notification to NRC pursuant to 10CFR50.72.
S = 3 N/n % Where N is the number of SGs in the unit and n is the number of SGS inspected during inspection period.
(continued)
SAN ON0FRE--UNIT 2 5.0-19a Amendment No.
I PCN-489 1
l Attachment F PROPOSED TECHNICAL SPECIFICATIONS (Changesincorporated)
SAN ONOFRE UNIT 3 1
1
(,
4 I
4 1
T 4
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) e.
Inspection Frequency The above required inservice inspections of the non-repaired SG tubes shall be performed at the following frequencies:
1.
The first inservice inspection shall be performed af ter 6 effective full power months but within 24 calendar months of initial criticality.
Subsequent inservice l
inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection.
If two consecutive inspections, not including the preservice inspection, result in all inspections results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months; 2.
If the results of the inservice inspection of a SG conducted in accordance with Table 5.5.2.11-1 at 40-month.
intervals fall in Category C-3, the inspection shall be increased to at least once per 20 months. The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of Specification 5.5.2.11.e.1, the interval may then be extended to a maximum of once per 40 months; and 3.
Additional, unscheduled inservice inspections shall be performed on each SG in accordance with the first sample inspection specified in Table 5.5.2.11-1 during the shutdown subsequent to any of the following conditions:
a)
Primary-to-secondary tubes leak (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Technical Specification 3.4.13, or b)
A seismic occurrence greater than the Operating Basis Earthquake, or c)
A loss-of-coolant accident requiring actuation of the Engineered Safety Features, or d)
A main steam line or feedwater line break.
(continued)
SAN ON0FRE--UNIT 3 5.0-16 Amendment No.
1 1
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued)
I j)
Tube Repair - refers to a process that reestablishes tube serviceability. Acceptable tube repairs will be performed by the following processes:
l i)
TIG welded sleevir.g as described in AB8/CE l
Topical Report, CEN-630-P, Rev. 2, is currently approvedbytheNRCand/or
- 11) Laser welded sleeving as described in the NRC approved Westinghouse Topical Reports WCAP-13698 Rev. 2, WCAP-13698 Rev. 2 Addendum 1, and WCAP-15014.
Tube repair includes the installation by welding of the sleeves, heat treatment in accordance with CEN-630-P,Rev.2,and/orWCAP-13698,Rev.2toremove
[
the stresses that are introduced by the sleeve installation, acceptance testing of the sleeve, and nondestructive examination for future comparison.
Tube repair can be performed on certain tubes that have been previously plugged as a corrective or preventive measure.
A tube inspection of the full length of the tube shall be performed on a previously plugged tube prior to returning the tube to service.
2.
The SG shall be determined OPERABLE af ter completing the corresponding actions (plug or repair all tubes exceeding the repair limit and all tubes containing through-wall cracks, and plug all sleeved tubes that exceed the repair criteria) required by Tables 5.5.2.11-1 and 5.5.2.11-2.
g.
Reports The content and frequency of written reports shall be in accordance with Technical Specification 5.7.2, "Special Reports."
i i
G i
(continued)
SAN ON0FRE--UNIT 3 5.0-19 Amendment No.
l
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.11 Steam Generator Tube Surveillance Program TABLE 5.5.2.11-1 (page 1 of 1)
STEAM GENERATOR TUBE INSPECTION SUPPLEMENTAL SAMPLING REQUIREMENTS 1st Sample Inspection 2nd Sample Inspection 3rd Sample Inspection Action Action Action Sample Site Result Required Result Required Result Required A minimum of C-1 None N/A N/A N/A N/A 5 tubes per 5G C-2 Plug or repair C-1 None N/A N/A by sleeving defective tubes Plug or repair by l
and inspect an sleeving additional 25 defective tubes C-1 None l
tubes in this and inspect an SG.
additional 45 C-2 Plug or repair tubes in this SG.
by sleeving defective tubes.
C-3 Perform action for C-3 result of first sample.
C-3 Perform N/A N/A action for s
C-3 result of 1
first sample.
C-3 Inspect all All other SGs None N/A N/A tubes in this C-1 SG, plug or repair by sleeving Some SGs C 2 Perform N/A N/A defective tubes but no other action for and inspect 25 is C-3 C-2 result of tubes in each second other SG.
sample.
Notification to NRC Additional SG Inspect all tubes pursuant to is C-3 in each SG and N/A N/A 10CFR50.72 plug or repair by sleeving defective tubes.
Notification to NRC pursuant to 10CFR50.72.
S=3N/n%WhereNisthenumberofSGsintheunitandnisthenumberof SGs inspected during inspection period.
(continued)
SAN ON0FRE--UNIT 3 5.0-19a Amendment No.
a
~
PCN-489 F
e Attachment G PROPOSED BASES CHMIGES (For information only)
(Strike out for deletions and highlight for additions.)
SAN ONOFRE UNIT 2 l
T u
l i
I r
s 4
i e
i i
m-m
--+i-'-
- m
---r
RCS Operational LEAKAGE B 3.4.13 BASES (continued)
LC0 relationship between leakage limits and tube (continued) degradation and sleeving is discussed in the following section f.
Primary to secondary LEAKAGE must be included in the total allowable limit for identified LEAKAGE.
e.
Primary to Secondary LEAKAGE throuah Any One SG The 720 gallon per day limit on primary to secondary LEAKAGE through any one SG allocates the total 1 gpm allowed primary to secondary LEAKAGE equally between the two generators. A limit of 150 Gallons per day through any one steam generator is imposed on Unit 2 following installation of steam generator tube sleeves.
f.
Steam generator tube degradation such as stress corrosion cracking defects may occur and propagate from inside or from the outside of the tubes, particularly in the areas within the tubesheet and immediately above the tubesheet.
Stress corrosion cracking is also seen in U-bends and in the tubes within the tube support eggcrates.
Crack-like indications shall be removed from service by plugging or.
repaired by sleeving.
The technical bases for TIG welded sleeving is described l
inthecurrentNRCapproved'ABB-CETechnicalreport-Tubes Using Leak Tight Sleeves." /4" 0.0 Steam Generator CEN-630-P Revision 2 ' Repair of 3 This includes the installation process and heat treatment process.
Heat treatment at 1300*F to 1425*F will be performed for 3 to 5 minutes to reduce residual stresses.
The qualification of the sleeves for eddy current examination of the sleeve /tubepressureboundaryisdescribedinABB-CE report 96-0SW-003-P Revision 00, "EPRI Steam Generator Examination Guidelines Appendix H Qualification for Eddy Current Plus-Point Probe Examination of ABB-CE Welded Sleeves."
f Th'e" technical bases"foiliser Velded"s1'eevMg is dessibe'd Report WCAP-136980l approved Westinghouse Generic Sleevin in'the current NRC Rev.42M' Laser:WeldedSleevesifor3/4 InchDiameter,TubeFeedring-Type"andWestinghouseil Preheater.' Steam; Generators", WCAP-13698?Addendumil'tand WCAP.-15014 Revb1E" Specific Application?ofKlaser LWelded Sleeves for: Southern CaliforniaL EdisonTSani0nofre! Units 12 and13l Steam Generatorsi"'!This11ncludes:a description of the1 installation. process;and heatEtreatment process.
(continued)
SAN ON0FRE--UNIT 2 B 3.4-73 Amendment No. 127
RCS Operational LEAKAGE B 3.4.13 BASES (continued)
LC0 TiiEq'Gi)Tf fdfT6Ei6filliE3fiFv'ETY6 Middy fEU rFsst documen t eOyje s tli ng hop s_/ th b~eipf'e s s breib6u n examin~ationof?thi? sleeve
~~ ~ " " '
" ' ~ "
(continued) ef ~
The periods between inspections account for the growth of incipient cracking to ensure that cracks do not develop in service and grow to a size that would risk tube burst or sleeve burst during normal operating conditions or during accident or faulted conditions.
This methodology and the structural margin criteria are stated in Regulatory Guide 1.121.
In spite of steam generator repair and analysis to restore and demonstrate adequate margins against tube rupture, leakage has been experienced from tubes and sleeves in PWR steam generators. Active steam generator tube degradation increases the probability of leakage. Active steam generator tube leakage has been seen in the industry to be a frequent precursor to tube rupture.
As an effort to reduce the frequency and consequences of tube ruptures, Regulators and the industry have, as a conservative measure, developed primary-to-secondary steam generator tube leakage guidelines that entail lower primary-to-secondary leakage limits from steam generator tubes.
These lower limits are documented in EPRI TR-104788, "PWR Primary-to-Secondary Leak Guidelines" which describes leak measurement methods and limitations. A primary-to-secondary leakage limit of 150 GPD per steam generator is a conservative and achievable detection limit.
Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tube will be located and plugged or repaired by sleeving.
APPLICABILITY In MODES 1, 2, 3, and 4, the potential for RCPB LEAKAGE is i
greatest when the RCS is pressurized.
In MODES 5 and 6, LEAKAGE limits are not required because the i
reactor coolant pressure is far lower, resulting in lower stresses and reduced potentials for LEAKAGE.
e a
I t
7 (continued)
- SAN ON0FRE--UNIT 2 B 3.4-74 Amendment No. 127 1
I'
l I
~
RCS Operational LEAKAGE B 3.4.13 BASES (continued)
ACTIONS Ad Unidentified LEAKAGE, identified LEAKAGE, or primary to secondary LEAKAGE in excess of the LC0 limits must be reduced to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. This Completion Time allows time to verify leakage rates and either identify unidentified LEAKAGE or reduce LEAKAGE to within limits before the reactor must be shut down. This action is necessary to prevent further deterioration of the RCPB.
B.1 and B.2 If any pressure boundary LEAKAGE exists or if unidentified, identified, or primary to secondary LEAKAGE cannot be reduced to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, the reactor must be brought to lower pressure conditions to reduce the severity of the LEAKAGE and its potential consequences.
The reactor must be brought to MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. This action reduces the LEAKAGE and also reduces the factors that tend to degrade the pressure boundary.
The allowed Completion Times are reasonable, based on operating experience, to reach the required conditions from full power conditions in an orderly manner and without challenging plant systems.
In MODE 5, the pressure stresses acting on the RCPB are much lower, and further deterioration is much less likely.
SURVEILLANCE SR 3.4.13.1 REQUIREMENTS Verifying RCS LEAKAGE to be within the LC0 limits ensures the integrity of the RCPB is maintained.
Pressure boundary LEAKAGE would at first appear as unidentified LEAKAGE and can only be positively identified by inspection.
Unidentified LEAKAGE and identified LEAKAGE are determined by performance of an RCS water inventory balance.
Primary to secondary LEAKAGE is also measured by aerformance of an RCS water inventory balance in conjunction witi effluent monitoring within the secondary steam and feedwater systems. This requirement is typically satisfied continuously by a radiation annunciator which detects primary to secondary leakage not being in the alarm state.
The RCS water inventory balance must be performed with the reactor at steady state operating conditions. Therefore, this SR is not required to be performed in MODES 3 and 4, until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of steady state operation have elapsed.
(continued)
SAN ON0FRE--UNIT 2 B 3.4-75 Amendment No. 127 j
' 3.4.13 3
BASES (continued) l SURVEILLANCE SR 3.4.13.1 (Continued)
REQUIREMENTS
. Steady state operation is required to perform a proper water inventory balance; calculations during maneuvering are not useful and a Note recuires the Surveillance to be met when steady state i
is establishec.
For RCS operational LEAKAGE determination-by i
water inventory balance, steady state is defined as stable RCS pressure, temperature, power level, pressurizer and makeup tank levels, makeup and letdown, and RCP seal injection and return l
flows.
An early warning of 3ressure boundary LEAKAGE or unidentified j
LEAKAGE is provided ]y the automatic systems that monitor the containment atmos)here radioactivity and the containment sump j
l evel. These leacage detection systems are specified in LC0 3.4.15, "RCS Leakage Detection Instrumentation."
1 The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Frequency is a reasonable interval to trend LEAKAGE and recognizes the importance of early leakage detection in the prevention of accidents. A Note under the Frecuency column states that this SR is required to be performec during steady d
state operation.
If a transient evolution is occurring 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from the last water inventory balance, then a water inventory balance shall be 1
j performed within 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> of the last water inventory balance.
This SR provides the means necessary to determine SG OPERABILITY in an operational MODE. The requirement to demonstrate SG tube i
integrity in accordance with the Steam Generator Tube Surveillance Program emphasizes the importance of SG tube integrity, even though this Surveillance cannot be performed at normal operating conditions.
REFERENCES 1.
10 CFR 50, Appendix A, GDC 30.
2.
Regulatory Guide 1.45, May 1973.
3.
UFSAR, Section 15.
~
l 4
SAN ONOFRE--UNIT 2 B 3.4-75a Amendment No. 127
PCN-489 4
Attachment H PROPOSED BASES CHANGES (Forinformationonly)
(Strike out for deletions and highlight for additions.)
SAN ONOFRE UNIT 3 l
l l
I e
j i
i i
w r.
r
^
RCS Operational LEAKAGE B 3.4.13 j
BASES LC0 relationship between leakage limits and tube (continued) degradation and sleeving is discussed in the following section f.
Primary to secondary LEAKAGE must be included in the total allowable limit for identified LEAKAGE.
e.
Primary to Secondary LEAK GE throuah Any One SG The 720 gallon per day limit.on primary to secondary LEAKAGE through any one SG allocates the total 1 gpm allowed primary to secondary LEAKAGE equally between the two generators. A limit of 150 Gallons per day through any one steam generator is imposed on Unit 3 following installation of steam generator tube sleeves.
f.
Steam generator tube degradation such as stress corrosion cracking defects may occur and propagate from inside or from the outside of the tubes, particularly in the areas within the tubesheet and immediately above the tubesheet.
Stress corrosion cracking is also seen in U-bends and in the tubes within the tube support eggcrates.
Crack-like indications shall be removed from service by plugging or repaired by sleeving.
The technical bases for TIG Mdid sleeving is described l
in the current NRC approved /P8 CE Technical report -
CEN-630-PRevision2"Repairof3/4"0.D.SteamGenerator Tubes Using Leak Tight Sleeves." This includes the installation process and heat treatment process.
Heat treatment at 1300"F to 1425*F will be performed for 3 to 5 minutes to reduce residual stresses.
The qualification of the sleeves for eddy current examination of the sleeve /tubepressureboundaryisdescribedinABB-CE report 96-0SW-003-P Revision 00, "EPRI Steam Generator Examination Guidelines Appendix H Qualification for Eddy Current Plus-Point Probe Examination of ABB-CE Welded l
Sleeves."
Thei tectihihal " basis?fdr?1 as eriel ded isl e'evi ng [i s?desbri bsd
~
in the current NRC: approved lWestinghouseiGenericiSleeving Report,,WCAPs13698,Rev.I2" Laser;WeldedS1eevesLfor33/4 J
InchiDiameterjTubeFeedr.ing"-;TypelandWestinghous'e;._
Preheater; Steam Gen'erators",?WCAP 13698 Addendum?1,Kand WCAP-150141Revb1x"SpecificL Application'.offlaser Welded Sleeves ?for; Southern 4 California' EdisoniSatii0nofreL Unitsi2
~
and 3 Ste'am Generators."!>This" includes a" description!of theiinstallation.processia'ndfheat'treatmentprocess.
(continued)
[
SAN ON0FRE--UNIT 3 8 3.4-73 Amendment No. 116 d
RCS Operational LEAKAGE B 3.4.13 BASES LC0 TliE3tia.lif Eafi66I6f 5tisii}ili~diT5i"f6i7EddjRuFMrit
~
(continued) examisation of(theTsleeve/tubejp~fessurelboundarif hisibieh
' ~ ~ ~ ~ ' ~ ' "
documentedtbyiWestinghousej ~
The periods between inspections account for the growth of incipier.t cracking to ensure that cracks do not develop in service and grow to a size that would risk tube burst or sleeve burst during normal operating conditions or during accident or faulted conditions.
This methodology and the structural margin criteria are stated in Regulatory Guide 1.121.
In spite of steam generator repair and analysis to restore and demonstrate adequate margins against tube rupture, leakage has been experienced from tubes and sleeves in PWR steam generators. Active steam generator tube degradation increases the probability of leakage. Active steam generator tube leakage has been seen in the industry to be a frequent precursor to tube rupture. As an effort to reduce the frequency and consequences of tube ruptures, Regulators and the industry have, as a conservative measure, developed primary-to-secondary steam generator tube leakage guidelines that entail lcwer primary-to-secondary leakage limits from steam generator tubes.
These lower limits are documented in EPRI TR-104788, "PWR Primary-to-Secondary Leak Guidelines" which describes leak measurement methods and limitations. A primary-to-secondary leakage limit of 150 GPD per steam generator is a conservative and achievable detection limit.
Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tube will be located and plugged or repaired by sleeving.
APPLICABILITY In MODES 1, 2, 3, and 4, the potential for RCPB LEAKAGE is greatest when the RCS is pressurized.
In MODES 5 and 6, LEAKAGE limits are nct required because the reactor coolant pressure is far lower, resulting in lower stresses and reduced potentials for LEAKAGE.
(continued)
SAN 6dOFRE--UNIT 3 B 3.4-74 Amendment No. 116
RCS Operational LEAKAGE B 3.4.13 BASES ACTIONS
/L1 Unidentified LEAKAGE, identified LEAKAGE, or primary to secondary LEAKAGE in excess of the LC0 limits must be reduced to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. This Completion Time allows time to verify leakage rates and either identify unidentified LEAKAGE or reduce LEAKAGE to within limits before the reactor must be shut down. This action is necessary to prevent further deterioration of the RCPB.
B.1 and B.2 If any pressure boundary LEAKAGE exists or if unidentified, identified, or primary to secondary LEAKAGE cannot be reduced to within limits witnin 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, the reactor must be brought to lower pressure conditions to reduce the severity of the LEAKAGE and its potential consequences. The reactor must be brought to MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
This action l
reduces the LEAKAGE and also reduces the factors that tend to degrade the pressure boundary.
The allowed Completion Times are reasonable, based on operating experience, to reach the required conditions from full power conditions in an orderly manner and without challenging plant systems.
In MODE 5, the pressure stresses acting on the RCPB are much lower, and further deterioration is much less likely.
SURVEILLANCE SR
- 3. 4 1L.1 REQUIREMENTS Verifying RCS LEAKAGE to be within the LC0 limits ensures the integrity of the RCPB is maintained.
Pressure boundary LEAKAGE would at first appear as unidentified LEAKAGE and can only be positively identified by inspection.
Unidentified LEAKAGE and identified LEAKAGE are determined by performance of an RCS water inventory balance.
Primary to secondary LEAKAGE is also measured by performance of an RCS water inventory balance in conjunction with effluent monitoring within the secondary steam and feedwater systems. This requirement is typically satisfied continuously by a radiation annunciator which detects primary to secondary leakage not being in the alarm state.
The RCS water inventory balance must be performed with the reactor at steady state operating conditions.
Therefore, this SR is not required to be performed in MODES 3 and 4, until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of steady state operation have elapsed.
(continued)
SAN ON0FRE--UNIT 3 B 3.4-75 Amendment No. 116
^
RCS Operational LEAKAGE B 3.4.13 BASES SURVEILLANCE SR 3.4.13.1,(continued)
REQUIREMENTS Steady state operation is required to perform a proper water inventory balance; calculations during maneuvering are not useful and a Note requires the Surveillance to be met when steady state is established.
For RCS operational LEAKAGE determination by water inventory balance, steady state is defined as stable RCS pressure, temperature, power level, pressurizer and makeup tank levels, makeup and letdown, and RCP seal injection and return flows.
An early warning of pressure boundary LEAKAGE or unidentified LEAKAGE is provided by the automatic systems that monitor the containment atmosphere radioactivity and the containment sump l evel. These leakage detection systems are specified in LC0 3.4.15, "RCS Leakage Petection Instrumentation."
The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Frequency is a reasonable interval to trend LEAKAGE and recognizes the importance of early leakage detection in.the prevention of accidents.
_A Note under the Frequency column states that this SR is required to be performed during steady j
state operation.
If a transient evolution is occurring 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from the last water inventory balance, then a water inventory balance shall be performed within 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> of the last water inventory balance.
SR 3.4.13.2 This SR provides the means necessary to determine SG OPERABILITY in an operational MODE. The requirement to demonstrate SG tube integrity in accordance with the Steam Generator Tube Surveillance Program emphasizes the importance of SG tube integrity, even though this Surveillance cannot be performed at normal operating conditions.
l REFERENCES 1.
10 CFR 50, Appendix A, GDC 30.
2.
Regulatory Guide 1.45, May 1973.
3.
UFSAR, Section 15.
t SAN ON0FRE--UNIT 3 B 3.4-75a Amendment No. 116
I i
i
)
ENCLOSURE 3 WESTINGHOUSE AFFIDAVITS FOR PROPRIETARY REPORTS i