ML18033A379
| ML18033A379 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/23/1988 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML18033A380 | List: |
| References | |
| TAC-R00460, TAC-R460, NUDOCS 8809290002 | |
| Download: ML18033A379 (7) | |
Text
TENNESSEE VALLEYA HORITY CHATTANOOGA. TENNESSEE 3740 5M 157B Lookout Place g(
IRP. 28 l98B U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
In the Matter of Tennessee Valley Authority
)
)
)
Docket Nos.
50-259 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) UNITS 1, 2, AND 3 SAFETY SYSTEM FUNCTIONAL INSPECTION (SSFI)
REPORT'O.
BFA 88811 TVA is submitting the sub)ect report as requested by G.
E. Gears, TVA Pro)ect
- Manager, NRC Office of Special Pro]ects.
SSFI Report No.
BFA 88811 considers the emergency equipment cooling water (EECW) and the residual heat removal service water (RHRSW) to be functional.
The inspection was a TVA managed task with )oint participation by TVA and ERC International.
Currently, affected BFN organizations are preparing recommendations. for each inspection observation.
These recommendations and subsequent corrective actions should provide confidence in the functional readiness and restart of BFN.
The enclosures contain proprietary information and should be withheld from public disclosure as provided in 10 CFR 2.790.
They are, therefore, deemed to be commercial or financial information with the meaning of 10 CFR 9.5(a)(4) and shall be subject to public disclosure only in accordance with the provisions of 10 CFR 9.12.
If you have any questions, please telephone Wayne Ivey at (205) 729-2071.
Very truly yours, 4
TENN S
E VA AUTHORITY t
Enclosures cc:
See page 2
R. L. Gridley Manager Nuclear Licensing and Regulatory Affairs
/+leap
4
U.S. Nuclear Regulatory Commission SRP 28 1888 cc: (Enclosures)
Mr. F.
R. McCoy, Acting Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. S.
C. Black, Assistant Director W for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20B52
'rowns Ferry Resident Inspector Browns Ferry Nuclear Plant Route 12, P.O.
Box 637,
- Athens, Alabama 35611
1
-" $ r
0 ichment I
BROMNS FERRY SSFI TION OBSERVATIONS S
Y OLD r
MR (7/28/88) 0
" OBSERVATION/ITFH MCS-1
'CS-2 MCS-3 MCS-4 MCS-5 MCS-6
'CS-7 (67-32)
(23-46)
(23-47)
(23-61)
(67-69)
(23-64)
(23-72)
Nonperformance of preventive maintenance on equipment, Rev.
1 Discrepancies in preventive maintenance for HOVs, Rev.
0 Meak housekeeping and maintenance practices, Rev.
1 Failure analysis not adequate to determine root causes, Rev.
0 Hethod for upgrading maintenance procedure may be too narrowly focused, Rev.
1 Control and documentation of postmaintenance testing is weak, Rev.
1 Upper torque limits for service ~ater pumps mounting bolts.,
Rev.
1 880515 880514 880508 880510 880509.
880501 U/R 0,
'HK-1 SHK-2',
SHK-3 SHK-4 SHK-5 SHK-6 SHK-7 MAP-1 MAP-2 (67-31) 1 23-38) 23-37)
(67-54)
(67-53)
(23-59)
(23-69)
(23-30)
(67-74)
EECM may not be capable of providing required flows, Rev.
1 Traveling screens could become inoperable affecting RKRSM flow, Rev. 0 Safety related boundary valve not installed on U-3 heat exchanger, Rev.
0 Isolation valves!FCV-67-50 and 51 may not close on demand, Rev. 2 Inadequacies in design analyses and testing for EECMs, Rev.
1 RHR heat exchanger relief valve may not be adequately sired, Rev.
0 Platforms, railings,and other equipment in the RHRSM pump rooms are not seismically anchored,Rev.
0 Incorrect relief valve settings for system piping, Rev.
0 Design pressure limitations for EECM components can be exceeded, Rev.
0 880419 871058 870872 880505 880491 880506 D/B P/L 2-1273 D/8 P/L 2-1264 D/8 P/L 2-1313
. SFK-1 SFK-2 SFK-3 SFK-4
. SFK-5 r'FK-6 (61-59)
(23&9)
(23-60)
(23-63)
(67-72)
(23-70)
Adequacy of 0-list as a controlled document, Rev.
0 D/G derating on high outside ambient temperature, Rev.
0 Inadequate motor OL heater selection for HOVs, Rev.
1 Lack of surveillance testing of motor thermal OL relays, Rev.
0 Meaknesses in dynamic load study for standby D/Gs, Rev.
0 Inadequacy of motor thermal OL calculation methodology, Rev.
0 870018 880447 PIR P BFN-EEB-8816 880516 PIR // BFN-EEB-8820 PIR 4 BFN-EEB<817 IV.
I e
1
~/
L BL-1 BL-2 BL-3 BLW BL-5 (67-58)
(23-48)
(67-61)
(61-62)
(23>>73)
Logic diagrams are not under configuration control, Rev.
1 Flow instruments are not qualified consistent with safety importance, Rev.
0 Flow transmitters installed in a harsh environmentjRev.
0
~ fs Press s~itches for EECM strainer start not seismically qualified, Rev.
1 Process instrumentation instructions do not provide for complete channel/loop calibration, Rev.
0 870657 880099 880511 U/R PIR // BFN-EEB-8815
Attac nt I
OLD GUN Page 2 0
V.
OBSERVATION/ITEN RB-1 RB-2
- RB-3 RB-4 (67-64)
Surveillances do not adequately verify EECH pump auto start, Rev.
1 (67-63)
No test to verify remote indicating lights for 67-50, 51, and 53, Rev.
0 (67-73)
Inadequacies in the flow balance of the EECM system, Rev.
0 (23-68)
Lack of adequate testing in the restart program for RHRSM and EECM, Rev.
0 870872 880472 880507 880472 VI.
, JJB-1 (67-41)
- JJB-2
~ 67-55)
JJB-3 (23-62)
'JB-4 (23-67)
'Heakness in operating instruction OI-67, Rev.
0 Failure to follow requirements of PHI 8.1, Temporary Alterations; Rev.
0 Failure to identify number of sump pumps for LCO. Rev.
0 Failure to folio~ PHI 12.12, Conduct of Operations, Rev.
0 880420 COTS D/8 P/L 20638 I
VII.
JLT 1
JLT-2 JLT-3 JLT-4 (67-60)
(23-65)
(23-66)
(67-71)
Drawings are nbt!being updated, Rev.
0 Meakness in plant'alve identification labels, Rev.
0 System status file is not being maintained current.
Rev.
0 Failure to notify operations personnel of 0/G load study calculations, Rev.
0 870657 880479 N
t
- Indicates plant agreement with CARR, but number not yet issued.
i D/8 P/L - Indicates design baseline punchlist item.
U/R Indicates observation still under revie~ by plant.
- I - Indicates area for improvement.
'OTS - Indicates item corrected on the spot.
~
PIR - 'Problem Investigation Report
~
~
0108F