ML20215G584
| ML20215G584 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/16/1987 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8706230306 | |
| Download: ML20215G584 (8) | |
Text
_ - - _ - _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _
TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 37401 SN 157B Lookout Place l
I JUN 161987 l
l TVA-SQN-TS-87-29 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
In the Matter of
)
Docket Nos. 50-327 Tennessee Valley Authority
)
50-328 SEQUOYAH NUCLEAR PLANT - TECHNICAL SPECIFICATION CHANCE 87 SUPPLEMENTAL INFORMATION j
Reference:
Letter from me to NRC dated May 15, 1987, "Sequoyah 4
l Nuclear Plant - Technical Specification Change 87-29" During a June 12, 1987 telephone conference call with T. Rotella, it was identified to TVA that several attachments to enclosure 2 referenced in the May 15, 1987 change package had not been received by NRC.
It was also stated that some additional information was required to justify the proposed change.
The attachments to enclosure 2 that were inadvertently omitted from the May 15, 1987 transmittal are included as enclosure 1. contains the requested additional justification for the proposed changes.
If you have any questions, please telephone Russell R. Thompson at (615) 870-7470.
Very truly yours, TENNESSEE VA EY AUTHORITY
/
l l
R. Gridley, Difector Nuclear Safety and Licensing Sworn to dsubscrAbedbeforeme thi
/d day of UM 1987 A&tt/)bkN
' Notary Public My Commission Expires Enclosures cc:
see page 2 f
8706D30306 870616 f[
PDR ADOCK 05000327 P
PDR An Equal Opportunity Employer
. U.S. Nuclear Regulatory Commission JUN 161987 oce (Enclosures):
Mr. Michael H. Mobley, Director (w/o Enclosures)
Division of Radiological Health T.E.R.R.A. Building 150 9th Avenue, N Nashville, Tennessee 37203 Mr. G. G. Zech, Assistant Director for Inspection Programs Office of Special Projects U.S. Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. J. A. Zwolinski, Assistant Director 1
for Projects Division of TVA Projects office of Special Projects U.S. Nuclear Regulatory Commission 4350 East West Highway EWW 322 Bethesda, Maryland 20814 Sequoyah Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379
i 1
1 ENCLOSURE 1 i
ATTACHHENTS TO DESCRIPTION AND JUSTIFICATION i
FOR TECHNICAL SPECIFICATION CHANGE I
-TVA-SQN-TS-87-29
..aw, a, ais-,e ta4,us w;,g,t.-w:,m ;g g
.s
l 1
ATTACHMENT 1 ACTIVE MOVs WITH BYFASSED TOL DEVICES 1,2-FCV-62-61 1,2-FCV-67-66 1,2-FCV-62-63 1,2-FCV-67-67 4
1,2-FCV-62-90 0-FCV-67-152 1,2-FCV-62-91 1,2-FCV-67-83
-1,2-LCV-62-132 1,2-FCV-67-87 j
1,2-LCV-62-133-1,2-FCV-67-88 1
l 1,2-LCV-62-135 1,2-FCV-67-95 1,2-LCV-62-136 1,2-FCV-67-96 1,2-FCV-74-12 1,2-FCV-67-91 1,2-FCV-74-24 1,2-FCV-67-103-1,2-FCV-63-39 1,2-FCV-67-104 1,2-FCV-63-40 1,2-FCV-67-99 1,2-FCV-63-25 1,2-FCV-67-111
.1.2-FCV-63-26 1,2-FCV-67-112 1
1,2-FCV-3-33 1,2-FCV-67-107
'1,2-FCV-3-47 1,2-FCV-67-130' 1,2-FCV-3-87 1,2-FCV-67-131 1,2-FCV-3-100 1,2-FCV-67-133 1,2-FCV-3-116A 1,2-FCV-67-134 1
1,2-FCV-3-116B 1,2-FCV-67-295 1,2-FCV-3-126A 1,2-FCV-67-296-1,2-FCV-3-126B 1,2-FCV-67-139 1,2-FCV-3-136A 1,2-FCV-67-297 1,2-FCV-3-136B 1,2-FCV-67-138
]
1,2-FCV-3-179A 1,2-FCV-67-142 1,2-FCV-3-179B 1,2-FCV-67-298 1,2-FCV-70-143 1,2-FCV-67-141 1,2-FCV-70-90 1,2-FCV-72-2 1,2-FCV-70-92 1,2-FCV-72-39 1,2-FCV-70-87 1,2-FCV-72-34 1,2-FCV-70-89 1,2-FCV-72-13 1,2-FCV-70-134 1,2-FCV-26-240 1,2-FCV-70-140 1,2-FCV-26-242 1,2-FCV-26-241 1,2-FCV-26-243 1,2-FCV-26-244
]
1,2-FCV-26-245
)
- na a x u.w a... a a w a u
1 ATTACHMENT 2 I
i MOVs NO LONGER ACTIVE BECAUSE OF APPENDIX R CONFICURATIONS I
1,2-FCV-62-98 1,2-FCV-62-99 1,2-FCV-70-4 0-FCV-67-151 1,2-FCV-67-223 1-FCV-67-424
{
0-FCV-67-478
..a c._wswn_s,a.._,.ua,,a w..a ssu
+
4 ATTACHMENT 3 1
l MOVs NO LONGER ACTIVE UNDER ASME SECTION XI PROGRAM l
1,2-FCV-63-118 1,2-FCV-63-98 1,2-FCV-63-80 1,2-FCV-63-67 1,2-FCV-67-65 1,2-FCV-67-68 1,2-FCV-70-133 1,2-FCV-70-139
\\
I 2
{
.:,-..+-_..__:.,
1 ATTACHMENT 4 ACTIVE MOVs ADDED TO TABLE 3.8-2 l
1
~
1,2-FCV-1-17 1,2-FCV-1-18 0-FCV-67-205 0-FCV-67-208 1
0-FCV-70-1 0-FCV-70-11 1,2-FCV-70-153 1,2-FCV-70-156 0-FCV-70-193 0-FCV-70-194 0-FCV-70-197 0-FCV-70-198 0-FCV-70-206 1,2-FCV-70-207 0-FCV-70-208 i
. }
u.
..._w
.. i
ENCLOSURE 2 SEQUOYAH NUCLEAR PLANT ADDITIONAL JUSTIFICATION FOR TECHNICAL SPECIFICATION CHANGE TVA-SQN-TS-87-29 i
The valves listed in attachment 2 are removed from table 3.8-2 because they are no longer considered to be active motor-operated valves (MOVs) because of 10 CFR 50 Appendix R configurations.
Power is normally removed from these valves. Power is verified to be removed from these valves once each 28 days by the performance.of Surveillance Instruction (SI)-708, "10 CFR 50 Appendix R Compliance Verification." These valves are not required to operate to perform any nafetp-related function. The centrifugal charging pump miniflow valves 1,2-FCV-62-98 and -99 (Final Safety Analysis Report [FSAR) figure 8.3.4-1) will have power applied to them momentarily for valve position verification purposes. This is normally perfctned before entry into Mode 4, but may be performed in any mode. Power is not normally applied to these valves at any time curing normal plant operations. The component cooling system (CCS) valves 1,2-FCV-70-4 (FSAR figure 9.2.1-1) will have power applied to them momentarily for the performance of SI-32, " Component Cooling Water Valves (Position Verification)." This test is performed once each 31 days on a staggered test basis in Mode 4 and above.
The essential raw cooling water (EECW) valves 0-FCV-67-151
-478, 1-FCV-67-424, and 1,2-FCV-67-223 (FSAR figure 9.2.2-2) will have power applied to them momentarily during the performance of SI-33. "ERCW Valves Servicing Safety Related Equipment (Common)." This SI is performed once each 31 days in Mode 4 and above.
Whenever power is applied to these valves, the action statement of specification 3.7.12 is applied. This requires the posting of a fire watch between the breaker and the valve within one hour.
The valves listed in attachment 3 are removed from table 3.8-2 because they are no longer considered to be active MOVs under the ASME Section XI program.
The cold-leg accumulator isolation valves 1,2-FCV-63-118, -98, -80, and -67 (FSAR figures 6.3.2-1) are not considered active since power is removed from these valves during power operation pursuant to surveillance requirement 4.5.1.1.1.c.
If power is applied to these valves during power operations, Action a. of specification 3.5.1.1 will be complied with.
Below Mode 3, the valves are not required to be operable. The ERCW valves 1,2-FCV-67-65 and -68 i
(FSAR figure 9.2.2-1) are not active MOVs since they are not required for safe i
'shutoown of the plant. The valves only provide operational flexibility to l
supply "A" train ERCW to the "B" train diesel generator sets and "B" train ERCW to the "A" train diesel generator sets. The CCS valves 1,2-FCV-70-133 and -139 (FFAR figure 9.2.1-3) are also not considered as active MOVs. These valves are in line with the series containment isolation valves for the CCS supply to the thermal barriers and the reactor coolant pump oil coolers, respectively.
These valves are not containment isolation valves themselves.
As such, they are not required to mitigate the consequences of an accident.
(
i
~
_a. -.~.-.- a m
_