ML20004B484
| ML20004B484 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 05/20/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20004B483 | List: |
| References | |
| NUDOCS 8105280345 | |
| Download: ML20004B484 (22) | |
Text
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UNITED STATES
'h NUCLEAR REGULATORY COMMISSION 7 { d( l j WASHINGTON, D. C. 20655
,f o
g;.v f OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMENDMENTTOFACILITYOPERATINGLICENF{
Amendment No. 59 License No. DPR-40 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Omaha Public Power District (the licensee) dated March 25, 1251 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commis: ion's rules and regulations set forth in 10 CFR Chapter ;
B.
The facility will operate in confonnity with the appli-cation, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
81052805/5 p.
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Accordingly, Facility Operating License No. DDR-40 is amended by changes to the Technical Specifications as 'nD.ated in the attachment to this license amendment, and para 3raph '4.B. of Facility Operating License No. DPR-40 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 59, are hereby incorporated in the license. The licensee shall operate the facility in accordance wtth the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION LIMA obert-A; Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: May 20, 1981
ATTACHMENT TO LICENSE AMENDMENT NO. 59 FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 Revise Appendix "A" Technical 3pecifications as indicated below. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Pages Insert Pages 2-73 through 2-73 through 2-78 2-78 2-81 through 2-81 through -
2-84 2-84 2-86 through 2-86 through 2-88 2-88 2-88a 3-77 3-77 3-78 3-78 3-79 3-79 3'-79a 5-19 5-19 l
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2.0 LIMITING CONDITIONS FOR OPERATION 2.18
,[ hock Suppressors (Snubbers)
Applicability This specification applies to safety-related shock suppressors (snubbers).
Operating Modes 1, 2 and 3 (Operating Modes 4 and 5 for snubbers located on systems required operable in those Operating Modes).
Obiective The objective is to specify modes of reactor operation for given conditions of safety-related snubbers.
Spscifications (1)
All snubbers listed in Table 2-6(a) and (b) shall be operable except as noted in 2.18(2) through 2.18(4) below.
(2)
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to operable status and perform sa engineering evaluation per Specification 3.14(3) on the supported component or declare the supported system inoperable and follow the appropriate actions specified in the Technical Specifications for that system.
(3)
A snubber may be removed for surveil ance in accordance with
{
Section 3.14(3) of these Technical Specifications, provided the following conditions are met:
(a)
A given snubber station shall not be without an operable snubber for more than two hours during surveillance of attendant snubber. A snubber may be replaced by an operable snubber during surveillance and repair.
(b)
No other snubber station, containing snubbers listed in Table 2-6(a) and (b), is known to be inoperable.
(c)
Only one snubber station, containing snubbers listed l
in Table 2-6(a)and (b), shall be removed for test-ing at a time to ensure that no two snubber stations are without an operable snubber during the same time interval.
1 (4)
Snubbers may be added, changed, or deleted from Table 2-6(a) and (b) without prior licensing amendments provided an accepted engineering analysis justifies each change. Deletions will be allowed only after an independent review of the cagineering justification is performed and the deletions are approved by SARC.
Any revisions to Table 2-6(a) and (b) will be included in subsequent licensing amendment requests.
Amendment No. 27, 48, 59 2-73 l
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i 2.0 LIMITING CONDITIONS FOR OPERATION 2.18 Shock Suppressors (Snubbers)
Basis Snubbers are designed to prevent unrestrained pipe motion under dynamic loads as might occur during an earthquake or severe transient, while allowing normal thermal motion during startup or shutdown. The consequence of an inoperable snubber is an in-crease in the probability of structural damage to piping as a result of a seismic, or other event, initiating dynamic loads.
It is therefore required that all snubbers required to protect the primary coolant system or any other safety system or com-ponent be operable during reactor operation.
Because the snubber protection is required only during low probability events, an inoperable period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for repairs or replacements and an inoperable period of two hours is allowed for surveillance.
Table 2-6 (a) and (b) lists the snubbers that are on safety-related l
systems. The snubbers that are listed as " Inaccessible During Nor-mal Operation" are located inside of the containment building and would require a significant expenditure in man-rems to inspect on a periodic basis. Revisions may be made to Table 2-6 (a) and (b) without prior notice provided that an engineering analysis justi-fies these changes.
Those snubbers listed as " Difficult to Remove for Functicnal Testing" are so listed because they are either:
(1) rated at greater than 50,000 lbs. force, (2) inaccessible due to surrounding structures, or (3) located such that an excessive amount of time and effort would be required to remove them for testing.
Amendment No. 27, 49' 59 2-74 v
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TABIZ 2-6 (a) l ACCESSIBILITY OF SAFETY-RELATED SYSTEM HYDRAULIC SNUBBERS Located Accessible In High Difficult to During Inaccessible Radiation Remove for
- Snubber Normal During Normal Areas During Functional No.
Elevation Operation Operation Shutdown Testing ACS-18 996' 8" X
ACS-112 1040' 0" X
X ACS-113 1D40' 0" X
X ACS-113A 1040' 0" X
X ACS-116 1031' 4" X
ACS-117 1031' 4" X
ACS-118 1031' 4" X
ACS-121 1031' 4" X
AOS-123 1031' 4" X
ACS-127A 1040' 0" X
X ACS-128 1040' 0" X
X l
ACS-299 1056' 4-11/16" X
ACS-299A 1056' 6" X
ACS-302 1056' 4-11/16" X
ACS-304 1056' 4-11/16" X
~
ACS-305 1056' 4-11/16" X
ACS-306
'1056' 4-11/16" X
ACS-307 1056' 4-11/16" X
ACS-313 1054' 11" X
l ACS-385 987' Sk" X
FWS-1 Top 1038' 6" X
X FWS-1 Bottom 1038' 6" X
X WS-1 A 1033' 6" X
X WS-1B 1033' Si" X
X l
WS-1C 1033' 5\\"
X X
WS-2 Top 1038' 6" X
X WS-2 Bottom 1038' 6" X
X Amendment No. ://,59 2-75
TABLE 2-6 (a)
(C:ntinutd)
Lsested Accessible In High Difficult to During Inaccessible Radiation Remove for
- Snubber Normal During Nomal Areas During Functional No.
Elevation Operation Operation Shutdown _
Testing WS-2A 1038' 6" X
X 4
WS-2B 1038' 5 "
X X
WS-2C 1038' 5\\"
X X
WS-3B-North 1038' 5\\"
X WS-3B-South 1033' 6" X
WS-7D-North 1038' 6
X WS-7D-South 1038' 6" X
WS-28 1002' 6" X
WS-29A 1002' 6" X
WS-30 1002' 6" X
WS-32 1005' 1" X
WS-32A 1005' 1" X
-J WS-33 1001' 6" X
WS-34 1001' 6" X
j WS-35 1005' 5" X
WS-36 1005' 5" X
WS-37 1005' 5" X
WS-38 1010' 0" X
WS-39 1012' 1" X
WS-64 1043' 0" X
WS-64A 1041' 0" X
l WS-643 1041' 0" X
WS-65 1049' 6" X
WS-66 1049' 6" X
WS-67 1049' 6" X
WS-68 1049' 6" X
WS-68A 1049' 6" X
WS-69 1049' 6" X
WS-71 1037' 6" X
Amendment No. 17/, 59 2-76
TABLE 2-6 (a) l (Centinutd)
Lecsted Accessible In High Difficult to During Inaccessible Radiation Remove for
- Snubber Normal During Normal Areas During Functional No.
Elevation Operation Operation Shutdown Testing WS-74 1053' 0" X
i' WS-75A 1053' 0" X
WS-78 1038' 4" X
WS-79 1049' 6" X
WS-80 1049' 6" X
WS-81 1049' 6" X
WS-83 1033' 4" X
WS-86A 999' 0" X
WS-87 999' 0" X
WS-88 999' 0" X
WS-88A 999' 0" X
WS-89 1002' 6" X
WS-90 1001' 6" X
WS-90A 1005' 6-5/8" X
WS-91 1019' 0" X
WS-92 1019' 0" X
~i WS-92A 1026' 0" X
WS-93 1032' 0" X
WS-94 1032' 0" X
WS-95 1032' 0" X
WS-96 1032' 0" X
X WS-97 1032' 0" X
X WS-98 1032' 0" X
X WS-100 1039' 0" X
WS-101 1039' 0" X
MSS-1 1054' 7" X
X MSS-2 1054' 8\\"
X X
MSS-3 1038' 0" X
MSS Top 1038' 6" X
X e
Amendment No. 27, 59 2-77
TABLE 2-6 (a)
(Ctntinu d)
L cettd Accessible In High Difficult to During Inaccessible Radiation Remove for
- Snubber Normal During Normal Areas During Functional No.
Elevation Operation Operation Shutdown Testing MSS-4 Bottom 1038' 6" X
X MS-5 1054' 7" X
X MSS-6 1054' 8\\"
X X
MSS-7 1038' 6" X
X MSS-8-Top 1038' 6" X
X MSS Bottom 1038' 6" X
X MSS-8A 1038' 6" X
X MSS-8B 1038' 6" X
X MSS-SC 1038' 6" X
X MSS-8D 1038' 6" X
X MSS-9 1040' 7" X
MSS-9A 1040' 7" X
MSS-9B-North 1033' 6" X
Y MSS-9B-South 1033' 6" X
MSS-13 1040' 7" X
l MSS-13A-East 1040' 0" X
MSS-13A-West 1040' 0" X
MSS-13B-North 1038' 6" X
MSS-13B-South 1038' 6" X
RCP-Al 1016' 0" X
RCP-A2 1016' 0" X
RCP-A3 1016' 0" X
RCP-A4 1016' 0" X
RCP-B1 1016' 0" X
RCP-B2 1016' 0" X
RCP-B3 1016' 0" X
RCP-B4 1016' 0" X
I Amendment No. M. 59 2-78
~
TABLE 2-6(a) l (Cratinutd)
L2cated Accessible In Hig'n Difficult to During Inaccessible Radiation Remove for
- Snubber Normal During Normal Areas During Functional No.
Elevation Operation Operation Shutdown Testing RCS-52 1007' 9" X
RWS-79 1046' 0" X
X RWS-128 998' 8\\"
X RWS-130 998' 8\\"
X RWS-131 998' 8 "
X SG-Al 1049' 0" X
X SG-A2 1049' 0" X
X SG-A3 1049' 0" X
X SG-A4 1049' 0" X
X.
SG-B1 1049' 0" X
X SG-B2 1049' 0" X
X SG-B3 1049' 0" X
X SG-B4 1049' 0" X
X SIS-1 979' 6" X
SIS-1A 979' 6" X
SIS-3 979' 6" X
i SIS-4 979' 6" X
SIS-4A 979' 6" X
SIS-5 979' 6" X
SIS-5A 979' 6" X
S-6 979' 6" X
.,IS-6A 979' 6" X
SIS-7 979' 6" X
SIS-8 979' 4" X
SIS-8B 979' 6" X
SIS-8C 979' 6" X
SIS-9 979' 6" X
SIS-9A 979' 6" X
SIS-9B 979' 6" X
SIS-10 983' 6" X
SIS-ll 983' 6" X
SIS-16 981' 6" X
SIS-16A 981' 6" X
SIS-17 979' 6" X
Amendment No.17, 59 2-81
TABLE 2-6(o) l (Ctatinued)
. Located Accessible In High Difficult to l During Inaccessible Radiation Remove for
- Snubber Normal During Normal Areas During Functional No.
Elevation Operation Operation Shutdown Testing i
SIS-17A 979' 6" X
i SIS-18 979' 6" X
SIS-19 979' 6" X.
SIS-20 979' 6" X
SIS-21 979' 6" X
SIS-21A 981' 6" X
SIS-21B 981' 6" X
SIS-21C 981' 6" X
SIS-22 981' 6" X
SIS-24 983' 6" X
SIS-24A 983' 6" X
SIS-26 979' 6" X
SIS-27 981' 6" X
SIS-27A 981' 6" X
SIS-27B 981' 6" X
SIS-28 980' 0" X
i SIS-28A 980' 0" X
SIS-29 980' 0" X
SIS-30 979' 6" X
SIS-30A 979' 6" X
S-31 981' 6" X
ciS-31A 981' 6" X
SIS-32 980' 0" X
SIS-32A 980' 0" X
SIS-32B 980' 0" X
SIS-33-Top 981' 6" X
SIS Bottom 981' 6" X
X SIS-34 980' 0" X
SIS-35-Top 980' 0" X
SIS,
Bottom 980' 0" X
SIS-36-Top 974' 6" X
Amendment No. 77, 59 2-82
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TABLE 2-6(a)
(C:ntinuId)
Escatcd Accessible In High Difficult tc During Inaccessible Radiation Remove for
- Snubber Normal During Normal Areas During Functional No.
Elevation Operation Operation Shutdown Testing SIS Bottom 974' 6" X
SIS Top 981' 6" X
SIS Bottom 981' 6" X
SIS-38 981' 6" X
X SIS-38B 981' 6" X
X SIS-38C 981' 6" X
X SIS Top 973' 0" X
SIS Bottom 973' 0" X
SIS-39A 973' 0" X
SIS Top 981' 6" X
'i SIS Bottom 981' 6" X
SIS-41A 979' 6" X
SIS-42 979' 6" X
S-42A 979' 6" X
DIS-43 979' 6" X
SIS-43A 979' 6" X
SIS-44 979' 6" X
SIS-44A 979' 6" X
SIS-44B 979' 6" X
SIS-44C 979' 6" X
SIS-45 974' 6" X
SIS-45A 979' 6" X
SIS-46 979' 6" X
SIS-47 979' 6" X
SIS-48 979' 6" X
SIS-49 979' 6" X
SIS-50 979'.i" X
Amendment No. /J, 59 2-83
TABLE 2-6(a)
(Ctatinu;d)
Escated Accessible In High Difficult tc During Inaccessible Radiation Remove for
- Snubber Normal During Normal Areas During Functional No.
Elevation Operation Operation Shutdown Testing SIS-53 997' 6" X
SIS-53A 997' 6" X
SIS-54 996' 6" X
SIS-55 996' 6" X
SIS-56 996' 6" X
SIS-56A 996' 6" X
SIS-57 995' 11-3/8" X
SIS-58 995' 11-3/8" X
SIS-59 996' 6" X
SIS-60 996' 6" X
SIS-63 990' 6" X
l!S-64 990' 6" X
SIS-65 990' 9" X
SIS-66 1000' 0" X
SIS-67 1000' 0" X
SIS-68 1001' 9-3/8" X
i SIS-69 1003' 6" X
X SIS-70 1000' 0" X
SIS-;&A 1002' 8" X
SIS-72 1002' 8" X
. S-73 1002' 8" X
SIS-74 1002' 8" X
I*
SIS-74A 1002' 8" X
SIS-75 1002' 8" X
SIS-76 997' 6" X
SIS-76A 997' 6" X
SIS-77 931' 0" X
SIS-77A 991' 0" X
SIS-78 991' 0" X
SIS-79 1001' 4" X
SIS-79A
.1001' 4" X
Amendment No. 77, 59 2-E4
TABLE 2-6(c) l (C:ntinund)
Locatsd Accessible In High Difficult to During Inaccessible Radiation Remove for
- Snubber Normal During Normal Areas During Functional No.
Elevation Operation Operation Shutdown Testing SISe101 991' 0" X
SIS-101A 991' 0" X
SIS-102 991' 0" X
SIS-103 1001' 4" X
SIS-104 1001' 4" X
SIS-104A 1001' 4" X
SIS-104B 1001' 4" X
SIS-115 1009' 5-3/4" X
SIS-116 1009' 5-3/4" I
SIS-117 1009' 5-3/4" X
SIS-117A 1009' 5-3/4" X
SIS-118 1009' 5-3/4" X
SIS-118A IJo9' 5-3/4" X
SIS-119 1006' 4-1/2" X
Top SIS-119 1006' 4-1/2" X
i Bottom SIS-120 1006' 4-1/2" X
SIS-121 1007' 10" X
SIS-122 1003' 0-1/8" X
'S-122A 1003' 0-1/3" X
etS-123 1003' 0-1/3" X
l SIS-124 1010' 4" I
SIS-127 1010' 4" X
l SIS-127A 1010' 10-1/2" X
SIS-129 1005' 5" X
SIS-130 1008' 2" X
SIS-132 1008' 2" X
l.
SIS 134 1003' 0" X
SIS-135 1003' 0" X
SIS-140 1008' 10" X
SIS-ISO 1008' 10" X
SIS-159A 1004' 3-1/6" X
SIS-161 1014' 0" X
Amendment No. 17, 59 2-86
TABI.I 2-6(c) l (C:ntinuid)
Lscated Accessible In High Difficult tc During Inaccessible Radiation Remove for
- Snubber Normal During Normal Areas During Fue:tional No.
Elevation Operation Operation Jhutdown Testing SIS-162 1014' 6" X
SIS-164 1014' 0" X
SIS-165 1014' 6" X
SIS-165A 1014' 6" X
Top SIS-165A 1014' 6" X
Bottom SIS-166 1014' 6" X
SIS-167 1014' 6" X
SIS-168 1014' 6" X
SIS-168A 1014' 6" X
Top SIS-168A 1014' 6" X
Bottom SIS-169 1007' 7" X
SIS-169A 1007' 7" X
i SIS-170 1007' 8" X
SIS-170A 1007' 5" X
SIS-172 1032' 0" X
SIS-173 1036' 8" X
S-174 1049' 2" X
1S-174A 1049' 6" X
SIS-174B 1051' 7-1/4" X
X SIS-174C 1052' 6" X
X SIS-174D 1063' 7-1/4" X
X SIS-174E 1064' 6" X
X SIS-175 1057' 0" X
X SIS-175A 105C' 5-1/2" X
SIS-176 1064t a"
X X
[
SIS-176B 1052' 6" X
X SIS-176C 1051' 7-1/4" X
X SIS-176D 1064' 6" X
X SIS-176E 1063' 7-1/4" X
X SIS-176G 1074' 0" X
X SIS-176H 1074' 0" X
X SIS-178 981' 6" X
(
Amendment No. E7 48, 59 2-87 1
TABLE 2-6(c) l (C2ntinued)
Locctcd Accessible In High Difficult tc During Inaccessible Radiation Remove for
- Snubber Normal During Normal Areas During Functional No.
Elevation Operation Operation Shutdown Testing SIS-183 4055' 9-1/2" X
SIS-184 979' 6" X
SIS-185 979' 6" X
SIS-187 983' 6" X
SIS-188 988' 6" X
SIS-202 1009' 0" X
SIS-204 995' 0" X
SIS-205 979' 6" X
SIS-206 983' 6" X
SIS-208 1003' 1-1/8" X
~
WDS-107 1004' 0" X
WDS-122-991' 6
X Right WDS-122-991' 6" X
Left
~i NOTE: Modifications to this cable due to changes in high radiation areas should be submitted to the NRC as part of the next licensing amendment request.
- Location ACS Auxiliary Coolant System FWS Feedwater System MSS Main Steam System RCP Reactor Coolant Pump RCS Reactor Coolant System RWS Raw Water System SG Steam Generator SIS Safety Injection System WDS Waste Disposal System Amendment No. AN, 59 2-88
TABLE 2-6(b)
ACCESSIBILITT OF SAFETY-RELATED SYSTEM MECHANICAL SNUBBERS Located Accessible In High Difficult tc During Inaccessible Radiation Remove for
% ubber Normal During Normal Areas During Functional No.
Elevation Operation Operation Shutdown Testing HCV-327-S 1025' X
HCV-329-S 1025' X
HCV-331-S 1025' X
HCV-333-S 1025' X
HCV-1040-S-1 1041' X
HCV-1040-S-2 1041' X
HCV-lb40-S-3 1041' X
HCV-1040-S-4 1041' X
HCV-1040-S-5 1041' X
RCS-3A 996' X
RCS-16 1015' X
RCS-29 1047' X
RCS-29A 1045' X
SIS-112-C 1111'-6" X
SIS-112-D 1111'-6" X
SIS-112-E 1111'-6" X
SIS-112-F 1111'-6" X
SIS-114-A 1074' X
IS-114-B 1074' X
S-114-E 1074' X
SIS-114-F 1074' X
A=endment No.59 2-88a
.I k.
-_ = -
3.0 SURVEILLANCE REQUIREMENTS 3.14 Shock Suppressors (Snubbers)
Applicability This specification applies to all hydraulic snubbers on the reactor coolant and safety-related systems listed in Table 2-6 (a) and (b).
Objective The objective of this specification is to insure the overall integrity and operability of safety-related hydraulic snubbers.
Specifications (1)
All hydraulic snubbers whose seal material has been de-monstrated by operating experience, lab testing or analysis to be compatible with the operating environment shall be visually inspected. This inspection shall include, but not necessarily be. limited to, inspection of the hydraulic fluid reservoir, fluid connections, and linkage connections to the piping and anchor to verify snubber operability.
In those locations where snubber movement can be manually induced without disconnecting the snubber, verify that the snubber has freedom of movement and'is not frozen up.
Visual inspections shall be performed in accordance with the following schedule:
Number of Hydraulic Snubbers Found Next Required Inoperable During Inspection or Inspection During Inspection Interval Interval 0
18 months i 25%
1 12 months i 25%
2 6 months + 25%
3, 4 124 days i 15%
i S, 6, 7 62 days i 25%
>8 31 days i 25%
The required inspection interval shall not be lengthened more than one step at a time.
Snubbers may be categorized in two groups, " accessible" or
" inaccessible" based on their accessibility for inspection during reactor operation. These two groups may be in-spected independently according to the above schedule.
(2)
All hydraulic snubbers whose seal materials are other than eythlene propylene or other material that has been de-monstrated to be compatible with the operating environment shall be visually inspected for operability every 31 days.
Amendment No. 28/, 59 3-77
,y w.--_w.%.,,-,.,-.,.v-,-
,,,,-e
,,,-.,%.,m----,.,
,,,e,.,-e,.,,,,., -
_,,,.,-re--,...
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m--
e.--%.--..
,,g,- - - -
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3.0 SURVEILLANCE REQUIREMENTS I.14 Shock Suppressors (Snubbers) (Continued),
1 (3)
At least once par 18 months 6uring shutdown, a represent-ative sample of 88 snubbers shall be functionally tested either in-place or in a bench test. For each number of snubbers above 3 sitich does not meet the functional test acceptance criteria, an additional sample selected according to the expression 22(a-3) shall be functionally tested, where a is the total number of snubbers found inoperable during the functional testing of the representative sample.
For each inoperable snubber found during a resample test, an additional 22 snubbers will be tested until no additional inoperable snubbers ara found within a sample or until all snubbers in Table 2-6 (a) and (b) have been functionally tested. ~ -
The representative sample selected for functional testint shall include the various configurations, operating en-vironments and the range of size and capacity of snubbers.
At least 25% of the snubbers in the representative sample shall include snubbers from any of the following enree categories:
(a)
The first snubber away from each reactor vessel nozzle.
(b)
Snubbers within 5 feet of heavy equipment (valva, pump, turbine, motor, etc).
(c)
Snubbers within 10 feet of the discharge from a safety relief valve.
Snubbers identified in Table 2-6 (a) and (b) as "Especially Difficult to Remove" or in "Eigh Radiation Zones During Shutdown" shall also be included in the representative sample.*
In addition to the regular sample, snubbers which failed the previous functional test shall be ratested during the next test period.
If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested. Test results of these snubbers may not be included for the resampling.
i
- Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was performed te qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.
Amendment No. 7J 59 3-78
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3.0 SURVEILLAN:'E REQUIREMENT _S, 3.14 Shock Suppressors (Snubbers) (Continued)
If any anubber selected for feactional testing either fails to lockup or f ails to move, i.e.,
is frozen in place, the cause will be evaluated.
If the cause is a manufacturer or design deficiency, appropriate actiou shall be taken for snubbers of the same design subject to the same defect to determine if any more defects exist. This testing requirement shall be indepen-dent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.
For any snubber (s) found locked up during normal operation or found inoperable following a seismic event, an engineering evalua-tion shall be performed on the components which are eupported by the snubber (s). The purpose of this engineering evaluation shall be to determine if the components supported by the snubber (s) were
'dversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service.
If the engineering evaluation shows the components to be capable of meeting the designed service without the failed snubber, that snubber may be deleted from service and Table 2-6(a) and (b) per Specification 2.18(4).
(4)
Snubber Service Life Monitoring A record of the service life of each snubber, the date at which the deaignated service life commences and the installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 5.10.2 m.
At least once per 18 months the installation and maintenance record for each snubber listed in Table 2-6(a) and (b) shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next acheduled snubber service life review.
If the indicated service life will be exceeded prior to the next scheduled snubber service life review, the snubber service life shall be re-evaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review. This re-evaluation, replacement er reconditioning shall be indicated in the records.
Basis All snubbers listed in Table 2-6(a) and (b) are required operable to ensure that the structural integrity of the reactor coolant system and s11 other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads. Snubbers excluded from this inspection program are those installed on non-safety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection. Inspections performed before that interval has elapsed may be used as a new reference Amendpent No. 27,59 3-79
t 3.0 SURVEILLANCE REQUIRDIENTS 3.14 Shock Suppressora (Snubbers) (Continued) point to determine the next inspection. However, the results of such early inspections perforced beform the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.
When a snubber is found locked up or frozen in place or when a snubber has been inoperable during a seismic event, an engineering evaluation shall be performed, in addition to the determination of the snubber mode of failure. The purpose of the engineering evaluation is to determine if any safety-related component or system has been adversely affected by the inoperability of the snubber. The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the cupported component or system.
To provide essurance of snubber functional reliability, a repre-sentative sample of the installed snubbers will be functionally tested during plant shutdowns at 18 month intervals. Selection of a representative sample according to the expression 35(1+c/2)*
provides a confidence level of approximately 95% chat 90% to 100%
of the snubbers in the plant will be operable within acceptance limits. Observed failures of these sseple snubbers shall require functional testing of additional units. For each number of snubbers above c which does not meet the functional test ac-ceptance criteria, an additional sample selected according to the expression 35(1+c/2)(2/(c+1))2(a-c) will be functionally tested, where a is the total number of snubbers found inoperable during the functional testing of the representative sample. Functional testing will continue according to the expression b(35(1+c/2)(2/(e+1))2) whera b is the number of snubbers found inoperable in the previous resample, until no additional inoperable snubbers are found within a sample or until all snubbers in Table 2-6 have been functionally tested.
Hydraulic snubbers and mechanical snubbers will each be treated as a different entity for the above surveillance programs.
The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring repla:ed, in high radiation area, in high temperature area, etc.).
The requirement to conitor the snubber service life is included to ensure that the snubbers periodically undergo a performance cvaluation in view of their age and operating conditions.. These records will provide statistical bases for future consideration of snubber service life.
The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.
- The value c will be arbitrarily chosen by the applicant and incorporated into the expression for the representative sample and for the resample prior to the issuance of the Technical Specifications.
3-79a Amendment No. 59
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.s 5.0 ADMINISTRATIVE CONTROLS 5.10.2 The following records shall be retained for the duration of the Facility Operating License:
a.
Records of drawing changes reflecting facility dcsign modifications made to systems and equipment described in the Final Safety Analysis Rep;tt.
b.
Records of new and irradiated fuel inventory, fuel trans-fers and assembly burnup histories.
Records of facility radiation and contamination surveys.
c.
d.
Records of radiation exposure for all individuals entering radiation control areas.
e.
Records of gaseous and liquid radioactive material re-leased to the environs, f.
Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.
g.
Records of training and qualification for current members of the plant staff.
g h.
Records of in-service inspections performed pursuant to these Technical Specifications.
1.
Records of Quality Assurance activities required by the QA Manual.
J.
Records of reviews performed for changes made to pro-cedures or equipment or reviews of tests e.nd experiments pursuant to 10 CFR 50.59.
k.
Records of meetings of the Plant Review Committee and the Safety Audit and Review Committee.
1.
Records of Environmental Qualification whieb are covered under the provisions of Section 5.12 of the.s Technical Specifications.
m.
Records of the service lives of all hydraulic and mechanical snubbers listed on Table 2-6 (a) and (b) including the date at which the service life commences and associated install-ation and maintenance records.
5.11 Radiation Protection Program Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations in-volving personnel radiation exposure.
gyWV/#WW//#dtWeV/2V//f#d 5-19 Amendment No. 59
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