ML20094S153
| ML20094S153 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 11/30/1995 |
| From: | BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19317C161 | List: |
| References | |
| NUDOCS 9512060046 | |
| Download: ML20094S153 (19) | |
Text
.,
I e
ATTACIIMENT (A-3) 6 i
I UNIT 1 MARKED-UP TECIINICAL SPECIFICATION PAGES Revised Pages:
3/4 4-10 3/4 4-13 3/4 4-14 j
3/4 4-16 l
B 3/4 4-4 i
Baltimore Gas & Electric Company Docket Nos. 50-3t7 and 50-318
'~
November 30,1995 4
. 9512060046 951130 POR ADOCK 05000317 P.
., PDR
3/4.4 REACTOR C0OLANT SYSTEM t
3/4.4.5 STEAM GENERATORS LIMITING CONDITION FOR OPERATION 3.4.5 Each steam generator shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION: With one or more steam generators inoperable, restore the inoperable generator (s) to 0PERABLE status prior to increasing T., above 200 F.
SURVEILLANCE REQUIRENENTS 4.4.5.0 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4 0.5.
i 4.4.5.1 Steam Generator Sample Selection and Inspection - Each steam generator shall be detemined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generaters specified in Table 4.4-1.
I 4.4.5.2 Steam Generator Tube Sample Selection and Inspection - The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.4-2.
The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.4.5.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.5.4.
The tubes selected for each inservice inspection shall include at leas
% of the total number of tubes in all steam generators; the tubes selected for these inspections shall be selected on a random basis except:
J a.
Where experience in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from these critical areas.
b.
The first inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
1.
All nonplugged tubes that previously had detectable wall penetrations (> 20%), and CALVERT CLIFFS - UNIT 1 3/4 4-10 Amendment No.
l
j 3/4.4 REACTOR COOLANT SYSTEM i
i SURVEILLANCE REQUIREMENTS (Continued) i i
4.4.5.4 Acceptance Criteria g2 a.
As used in this Specification:
d u
r 2
Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or specifications.
Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections, j
1
Dearadation means a service-induced cracking,
wastage, wear or general corrosion occurring on either inside or outside of a tube.
l JK Dearaded Tube means a tube containing imperfections t 20% of l
lj the nominal wall thickness caused by degradation.
j
.L 4 Dearadation means the percentage of the tube wall thickness a
affected or removed by degradation.
l Defect means an imperfection of such severity that it exceeds the pluggindflimit. A tube containing a defect is defective.
i LI Any tube which does not permit the passage of the eddy-D
{
l current inspection probe shall be deemed a defective tube.
j i
means the imperfection de th a i
I which the tu ecause it may become un en s
of the nominal tube wall thickness.
t 8 [ Unserviceable describes the condition of a tube if it le i
or contains a defect large enough to affect its structural i
integrity in the event of an Operating Basis Earthquake, a i
loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3.c, above.
i 9 [ Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around i
the U-bend to the top support of the cold leg.
i r
b.
The steam generator shall be determined OPERABLE after completing the corresponding actions (plu all tubes exceeding the pluggin limit and all tubes containing hrough-wall cracks) required by
}
Table 4.4-2.
Ol'Nflf J
CALVERT CLIFFS - UNIT 1 3/4 4-13 Amendment No.
l i
t I
i
i 3/4.4 REACTOR C00UUIT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) v/r=^
4.4.5.5 Reports l
Or rdpAire.)
f a.
Following each inservic inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Comission within 15 days pursuant to Specification 6.9.2.
j b.
Thecomplethresultsofthesteamgeneratortubeinservice inspection shall be included in the Annual Operating Report for the period in which this inspection was completed (pursuant to Specification 6.9.1.5.b).
This report shall include:
j 1.
Number and extent of tubes inspected.
I 2.
Location and percent of wall-thickness penetration for each indication of an imperfection.
3.
Identification of tubes pluggedr QY j
c.
Results of steam generator tube inspections which fall into Category C-3 require verbal notification of the NRC Regional
)
l Administrator by telephone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to resumption of i
plant operation. The written followup of this report shall provide a description of investigations conducted to detennine cause of the tube degradation and corrective measures taken to i
prevent recurrence and shall be submitted within the next 30 days pursuant to Specification 6.9.2.
i l
i l
\\
J l
CALVERT CLIFFS - UNIT 1 3/4 4-14 Amendment No.
l
.m._
n TABLE 4.4-2 W
y Q Er Of ?Y Of Mf f N
I r-
^
STEAN GDIERATOR TUBE INSPECTION
_A i
15I 5ArrLL llDrtCIIUM 27K) 5APFLL I DVLCIIUM JMD 5MWLE IIOrLUllDR 38 O
Sample size Result Action Required Result Ac ;1on Required Result Ac1 1on Required S
5 4 minimum of 5 lubes per U-l None N/A N/A N/A N/A O
S. G.
C-Z PlugFdefective tubes and C-1
, Mone N/A N/A E
l inspect additional 25 c-z Plug' defective C-1 mone i
1 n
tubes in this S. G.
tubes and inspect pi,g " defective S
c.g z
additional 45 tubes tubes C
q in this S. G.
c-3 Pertom action for C-3 result of first sagle Of %8Y c-3 Perfom action for C-3 result of first N/A N/A g
sample c-3 Inspect all tubeutn All other this S. G., plugf S. G.s are None N/A N/A W
defective tubes and C-1 inspect 25 tubes in each a
other S. G.
e5 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> verbal 50me 5.ti.s rerfom action for N/A R/A notification to NRC with C-2 but no C-2 result of written followup additional second sample pursuant to S. G. are C-3 Specification 6.9.2.
Additional Inspect all tunes
~
S. G. is C-3 in each S. G. and ging defective N/A N/A tubes. 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> verbal notification to NRC with written a
followup pur uant g
to specification 6.9.2.
g E S = 3 h Where N is the number of steam generators in the unit, and n is the nuinber of steam generators inspected during an inspection w-es.+.y
3/4.4 REACTOR CC9LANT SYSTEM
- G BASES adequate structural margins against burst during all nonnal operating, transient, and accident conditions until the end of the fuel cycle. This 1
evaluation would include the following elements:
1.
An assessment of the flaws found during the previous inspections.
2.
An assessment of the structural margins relative to the criteria of l
Regulatory Guide 1.121. " Bases for Plugging Degraded PWR Steam Generator Tubes,' that can be expected before the end of the fuel cycle or 30 months, whichever comes first.
5 i
3.
An update of the assessment model, as appropriate, based on comparison of the predicted results of the steam generator tube integrity assessment with actual inspection results from previous inspections.
The plant is expected to be operated in a manner such that the secondary coolant will be maintained within those chemistry limits found to result in i
j negligible corrosion of the steam generator tubes.
If the secondary coolant chemistry is not maintained within these limits, localized 4
corrosion may likely result in stress corrosion cracking. The extent of i
cracking during plant operation would be limited by the limitation of steam i
generator tube leakage between the Primary Coolant System and the Secondary l
Coolant System (primary-to-secondary leakage = 1 gallon per minute, total).
y "9
Cracks having a primary-to-secondary leakage less than this limit during operation vill have an adequate margin of safety to withstand the loads s
imposed during nomal operation and by postulated accidents. Operating 2
plants have demonstrated that primary-to-secondary leakage of I gallon peminute can readily be detected by radiation monitors of steam generator i
blowdown.
Leakage in excess of this limit will require plant shutdown and j~
an unscheduled inspection, d g which the leaking tubes will be located and pluggeg.
d g
i Wastage-type defects are uni kely with proper chemistry treatment of the 1
L. 1 secondary coolant. However, even if a defect should develop in service, it will be found during scheduled inservice steam generator tube examinations.
Pluggings ill be required for all tubes with imperfections exceeding the w
piuaaincolimit of 40% of th tube nominal wall thickness. bSteam generator tube inspections of operati plants have demonstrated the capability to 3
g a;p reliably detect degradatio that has penetrated 20% of the original tube wall thicknessj ony.*A p:
W henever the result or in7 steam generator tubing inser e inspection fall into Category C-3, these results will be promptly reported to the Commission pursuant to Specifications 6.9.2 prior the resumption of plant i
i operation. Such cases will be considered by the Commission on a case-by-6 case basis and may resuit in a recuirement for anaiysis, iaboratory examinations, tests, additional ecdy-current inspection, and revision of the Technical Specifications, if necessary.
CALVERT CLIFFS - UNIT 1 B 3/4 4-4 Amendment No.
I
1 Insert A:
When applying the exceptions of 4.4.5.2.s through 4.4.5.2.c, previous defects or imperfections in the area repaired by sleeving are not considered an area requirmg i
reinspection.
j Insert B:
1.
Tubina or Tube means that portion of the tube or sleeve which forms the
(
primary system to secondary system pressure boundary l
t E
Insert C:
Pluneine or Raamir Limit 'ieans the invua:Ln f at or beyond which the-tube shall be removed from service by plawing, or repaired by sleeving in the affected area because it may become unserviceable prior to the next inspection.
l The plugging or repair limit imperfection depths are specified in percentage of i
nominal wall thickness as follows:
- a. original tube wall........ '............................................................
- b. Westinghouse laser welded sleeve wall..................................... 40%
i
i i
Insert D:
10.
Tube Repair refers to a process that reestablishes tube serviceability.
Acceptable tube repairs will be performed by the following processes:
l I.
Westinghouse Laser Welded Sleeving as described in a Westinghouse technical report currently approved by the NRC, subject to the limitations and restrictions as noted by the NRC staff;-
or i
I II.
ABB Combustion Engineering Leak Tight Sleeving as described m an ABB Combustion Engineering technical report currently i
approved by the NRC, subject to the limitations and restrictions as noted by the NRC staff.
Tube repair includes the removal of plugs that were previously installed as a j
corrective or preventive measure. A tube inspection per 4.4.5.4.a.9 is required j
prior to returnmg previously plugged tubes to service.
[
i l
t Insert E:
Defective tubes may be repaired by a Westinghouse Laser Welded Sleeve or an i
ABB Ccmbustion Engineering Leak Tight Sleeve. The technical bases for sleeving repair are described in the current Westinghouse and ABB Combustion Engineering technical reports.
[
t I
i
~.
Insert F:
If a tube contains a Westinghouse Laser Welded Sleeve with imperfection exceeding 40% of nominal wall thickness, or an ABB Combustion Engineering i
Leak Tight Sleeve with imperfection exceeding 40% of nominal wall thickness, it i
must be plugged. The basis for the sleeve plugging limit is based on Regulatory i
Guide 1.121 analyses, and is described in the Westinghouse and ABB Combustion Engineering sleeving technical reports mentioned above.
Insert G:
Repaired tubes are also included in the inservice tube inspection program.
h i.
l i
I l
s J
i ti t
h s
[
A i
4
1 l
ATTACHMENT (A-4) 4 t-i i
i UNIT 2 MARKED-UP TECHNICAL SPECIFICATION PAGES i
Revised Pages:
t i
3/4 4-10 8
l 3/4 4-13 l.
3/4 4-14 4
(
3/4 4-16 B 3/4 4-4 1
J l
4 i
i l
l Baltimore Gas & Electric Company Docket Nos. 50-317 and 50-318 November 30,1995
_. ~ _ _ _
1 3/4.4 REACTOR C0OLANT SYSTEM J 3 3/4.4.5 STEAM GENERATORS t
l LIMITING CONDITION FOR OPERATION l
3.4.5 Each steam generator shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4.
j ACTION: With one or more steam generators inoperable, restore the j
inoperable generator (s) to OPERABLE status prior to increasing T.,, above i
200 F.
j
]
I
$URVEILLANCE REQUIREMENTS 4.4.5.0 Each steam generator shall be demonstrated 0PERABLE by'perfomance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
1 4.4.5.1 Steam Generator Sample Selection and Inspection - Each steam generator shall be detemined 0PERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in i
w j y Table 4.4-1.
1 4.4.5.2 Steam Generator Tube Sample Selection and Inspection - The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.4-2.
The inservice inspection of steam generator tubes shall be perfomed at the l
frequencies specified in Specification 4.4.5.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.5.4.A The tubes selected for each inservice inspection shall include at i
least 3% of the total number of tubes in all steam generators; the tubes l
selected for these inspections shall be selected on a random basis except:
A Where experience in similar plants with similar water chemistry j
a.
indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from these critical areas.
t b.
The first inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
1.
All nonplugged tubes that previously had detectable wall j
penetrations (>20%), and 1
\\
1 i
- O CALVERT CLIFFS - UNIT 2 3/4 4-10 Amendment No.
l
+
I i
3/4.4 REACTOR C0OLANT SYSTEM
$URVEILLANCE REQUIREMENTS (Continued) 4.4.5.4 Acceptance Criteria i
- a. ps used in this Specification:
i 3 'g.
Imperfection means an exception to the dimensions, finish or l
contour.of a tube from that required by fabrication drawings l
cm or specifications. Eddy-current testing indications below i
20% of the nominal tube wall thickness, if detectable, may be j
considered as imperfections.
3
Dearadation means a service-induced cracking,
wastage, wear or general corrosion occurring on either inside or outside of a tube.
1 Dearaded Tube means a tube containing imperfections t 20% of the nominal wall thickness caused by degradation.
.h f
% Dearadation means the percentage of the tube wall thickness affected or removed by degradation.
j l
Defect means an imperfection of such severity that it exceeds i
L.
if j
f the plugginflimit. A tube containing a defect is defective.
Q j
Any tube which'does not pemit the passage of the eddy-current inspection probe shall be deemed a defective tube.
.q-l
'/
mit means the imperfection depth ce because it may which th a
of the nominal ube wall thic i
Unserviceable describes the condition of a tube if it leaks g
or contains a defect large enough to affect its structural l
integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line i
break as specified in 4.4.5.3.c, above.
I T
Tube Inspection means an inspection of the steam generator j
tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.
y b.
The steam generator shall be detemined OPERABLE after completing the corresponding actions (plu all tubes exceeding the plugging limit and all tubes containin hrough-wall cracks) required by i
Table 4.4-2.
l-L Q) l CALVERT CLIFFS - UNIT 2 3/4 4-13 Amendment No.
I 1
j 3/...' REACTOR COOLANT SYSTEM 1lh
$URVEILLANCE REQUIREMENTS (Continued) i or FT/MirdM j
. 4.5.5 Reports a.
Following each inservice nspection of steam generator tubes, the number of tubes plugged n each steam generator shall be reported to the Comission within 15 days pursuant to Specification 6.9.2.
y j
b.
The complete results of the steam generator tube inservice the period in which this insaction was completed (g Report f inspection shall be included in the Annual Operatin pursuant to l
Specification 6.9.1.5.b).
T11s report shall include:
1.
Number and extent.of tubes inspected.
i 4
2.
Location and percent of wall-thickness penetratiott for each
-ggf{
g}
i j
indication of an imperfection.
3.
Identification of tubes plugge.
l c.
Results of steam generator tube inspections which fall into l
Category C-3 require verbal notification of the NRC Regional Administrator by telephone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to resumption of plant operation.
The written followup of this report shall i
provide a description of investigations conducted to detemine cause of the tube degradation and corrective measures taken to
}
aQ prevent recurrence and shall be submitted within the next 30 days i
l pursuant to Specification 6.9.2.
1 i
l 1
f l
i a
4 2
,,.. 1.
nd nt...
~
__-..~.-_~n.-.
l t
C-v R
f gh y
TABLE 4.4-2
~g
.h STEAM GEllERATOR TUBE IllSPECTION Nf#_
j m
131 wd Kinrtsiaus snu hd al art.EIsequ sup 1_
4 i unrr.tiasui as j
h 5 ample 512e Result Action Required Result Ac',lon Required Result Act1 Dn equired S
i 5
R minimum of 5 lubes per C-1 Ront R/A N/A N/A N/A
-e
_s N/A N/A 3
S. G.
c-z Plug reefective tubes and C-1 inspect additional 25 c-z riug'aefective L-1 e
n pi,g r fective.
8 tubes in this S. G.
tubes and inspect ee additional 45 tubes C-2 tubes C
z Perform action 3':
I in this S. G.
Z C-3 for C-3 result' ro of first sample j
C-3 Perfotit action for i
gy psy)
C-3 result of first N/A N/A g
sample C-3 Inspect aII tuDes/in RII other this S. G., plugF S. G.s are Mone N/A N/A
}
R defective tubes and C-1 i
t a
inspect 25 tubes in each other S. G.
a
.L some 5. 5.s Perforill action for C-2 but no C-2 result of N/A N/A additional second sample 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> verbal S. G. are C-3 i
notification to NRC with written followup pursuant to Specification 6.9.2.
Additional Inspect all tunes S. G. is C-3 in each S. G. and L ugadefective N/A N/A l
y tWs. 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 3
[
rp verbal notification s
g hryp to MRC with written followup pursuant w
to Specification.
r+
6.9.2.
m o
S = 3 h Where N is the number of steam generators in the unit, and n is the number of steam generators l
3 inspected during an inspection i
euuump l
i 3/4.4 REACTOR COOLANT SYSTEM Q
BASES adequate structural margins against burst during all nonnal operating, transient, and accident conditions until the end of the fuel cycle. This evaluation would include the following elements:
1.
An assessment of the flaws found during the previous inspections.
4 2.
An assessment of the structural margins relative to the criteria of Regulatory Guide 1.121, " Bases for Plugging Degraded PWR Steam Generator Tubes," that can be expected before the end of the fuel cycle or 30 months, whichever comes first.
3.
An update of the assessment model, as ap)ropriate, based on comparison of the predicted results of t1e steam generator tube integrity assessment with actual inspection results from previous inspections.
i The plant is expected to be operated in a manner such that the secondary coolant will be maintained within those chemistry limits found to result in negligible corrosion of the steam generator tubes.
If the secondary coolant chemistry is not maintained within these limits, localized corrosion may likely result in stress corrosion cracking. The extent of cracking during plant operation would be limited by the limitation of steam generator tube leakage between the Primary Coolant System and the Secondary
^b Coolant System (primary-to-secondary leakage = 1 gallon per minute, total).
S/
Cracks having a primary-to-secondary leakage less than this limit during.
operation will have an adequate margin of safety to withstand the loads imposed during nonnal operation and by pcstulated accidents. Operating plants have demonstrated that primary-to-secondary leakage of 1 gallon per minute can readily be detected by radiation monitors of steam generator blowdown. Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugges. _
y repjg Wastage-type defects are unlikely with proper chemistry treatment of the secondary coolant. However, even if a defect should develop in service, it will be found during scheduled inservice steam generator tube examinations.
Plugging,will be required for all tubes with imperfections exceeding the VYb pluggingelimit of 40% of the tub nominal wall thickness, oSteam generator tube inspections of operating p1 ts have demonstrated the capability to reliably detect degradation that h penetrated 20% of the original tube wall thickness.4 gf.,
6 Whenever the resuits of any s eam generator tubing inservice inspection fall into Category C-3, these results will be promptly reported to the Comission pursuant to Specifications 6.9.2 prior to the resumption of plant operation. Such cases will be considered by the Comission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, tests, additional eddy-current inspection, and revision of the Technical Specifications, if necessary.
CALVERT CLIFFS - UNIT 2 B 3/4 4-4 AmendmentNo.[
]
l I
i Insert A:
When applying the exceptions of 4.4.5.2.a through 4.4.5.2.c, previous defects or imperfections in the area repaired by sleeving are not considered an area requiring j
reinspection.
Insen B:
1.
Iubing or Tube means that portion of the tube or sleeve which forms the f
primary system to secondary system pressure boundary l
l t
Insen C:
Phoeine or Reair Limit means the imperfection depth at or beyond which the l
tube shall be removed from service by plugging,_ or repaired by sleeving in the affected area because it may become unserviceable prior to the next inspection.
i The plugging or repair limit imperfection depths are specified in percentage of nominal wall thickness as follows:
I
- a. original tube wall..................................................................... 40%
- b. Westinghouse laser welded sleeve wall......................................... 40%
l
Insert D:
10.
Tube Repair refers to a process that reestablishes tube serviceability.
j Acceptable tube repairs will be performed by the following processes I.
Westinghouse Laser Welded Sleeving as described m a Westinghouse technical repon currently approved by the NRC, l
subject to the limitations and restrictions as noted by the NRC staff; or 1
l II.
ABB Combustion Engineering Leak Tight Sleeving as described in an ABB Combustion Engineering technical report currently approved by the NRC, subject to the limitations and restrictions as noted by the NRC staff.
Tube repair includes the removal of plugs that were previously installed as a corrective or preventive measure. A tube inspection per 4.4.5.4.a.9 is required prior to returning previously plugged tubes to service.
i Insert E:
Defective tubes may be repaired by a Westinghouse Laser Welded Sleeve or an ABB Combustion Engineering Leak Tight Sleeve. The technical bases for sleeving repair are described in the current Westinghouse and ABB Combustion Engineering technical reports.
i t
i I
1 T
l Ir. sert F:
If a tube contains a Westinghouse Laser Welded Sleeve with imperfection l
exceeding 40% of nominal wall thickness, or an ABB Combustion Engineering Leak Tight Sleeve with imperfection exceeding 40% of nominal wall thickness, it j
must be plugged. The basis for the sleeve plugging limit is based on Regulatory
[
Guide 1.121 analyses, and is described in the Westinghouse and ABB Combustion j
Engineering sleeving technical reports mentioned above.
1 i
1 Insert G:
Repaired tubes are also included in the inservice tube inspection program.
[
t I
f 4
5 1
i i
j 4
i l
1 i
a T
1 1
j I
1 i
ATTACIIMENT (B-1) 1 k
i 3
1 4
1 l
WESTINGHOUSE AUTHORIZATION LETTER, CAW-95-899, i
ACCOMPANYING AFFIDAVIT, PROPRIETARY INFORMATION NOTICE, j
i l
AND COPYRIGIIT NOTICE l
I l
1 1
i i
1 t
i i
Baltimore Gas & Electric Company l
Docket Nos. 50-317 and 50-318 November 30,1995
~,
i i
i.
Proprietary Information Notice l
^
I
.I Transmitted herewith are proprietary and/or non-proprietary versions of documents furnished to the NRC m connection with requests for generic and/or plant-specific review and approval.
i In order to conform to the requirements of 10 CFR 2.790 of the Commission's regulations concerning the f
~ protection of proprietary information so subnaitted to the NRC, the information which is proprietary in the l
proprietary versions is contained within brackets, ar4 where the proprietary information has been deleted in -
. the non-proprietary versions, only the brackets remain (the information that was contained within the brackets in the proprietary versions having been deleted). The justification for claiming the information so designated 4
as proprietary is indicated in both versions by means of lower case letters (a) through (f) contained within parentheses located as a superscript immediately following the brackets enclosing each item of information being identified as proprietary or in the margm opposite such information. 'Ihese lower case letters refer to l
the types of information Westinghouse customarily holds in confidence identified in Sections (4)(ii)(a) through g
(4)(ii)(f) of the affidavit accompanying this transmittal pursuant to 10 CFR 2.790(b)(1).
r 4
I l
l I
i l
t I
i i
~
nanausucasm
Copyright Notice ne reports transmitted herewith each bear a Westinghouse copyright notice. De NRC is permitted to make the number of copies of the information contained in these reports which are necessary for its internal use in connection with generic and plant-specific reviews and approvals as well as the issuance, denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a license, permit, order, or regulation subject to the requirements of 10 CFR 2.790 regarding restrictions on public disclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection notwithstanding. With respect to the non-proprietary versions of these reports, the NRC is permitted to make the number of copies beyond those necessary for its internal use which are necessary in order to have one copy available for public viewing in the appropriate docket files in the public document room in Washington, DC and in local public document rooms as may be required by NRC regulations if the number of copies submitted is insufficient for this purpose. Copies made by the NRC must include the copyright notice in all instances and the proprietary notice if the original was identified as proprietary.
MARLAS45UCAW-95-899