ML20100A908
| ML20100A908 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/30/1984 |
| From: | Foster D GEORGIA POWER CO. |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| GN-447, NUDOCS 8412040130 | |
| Download: ML20100A908 (9) | |
Text
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George Power Company Route 2, Box 299A Wayrosboro. Georgia 30830 1 Telephone 404 554-9061. Ext 3360 404 724 8114. Ext. 3360 D.'O. Foster
' Georgia Power Vice President and Project Generat Manager the southern electnc system Vogtle Project November 30, 1984 Assistant Director for Licensing File: X7BC35 Attention:
Ms. Elinor G. Adensam, Chief Log:
GN-447 Licensing Branch #4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 DRAFT SER OPEN ITEM RESPONSE SCHEDULE
REFERENCE:
Letter dated 11/6/84, T. M. Novak to D. O. Foster
Dear Mr. Novak:
-Your letter, referenced above, requested that a proposed schedule for written responses to the open items identified in the Draf t SER be provided..This schedule is attached. Please note that certain items have been identified as closed. It is my understanding that those items, which we have identified as clcsed, will be discussed in a meeting with your staff on December 13, 1984 to verify the item status.
If you have any questions concerning the attached information, do not hesitate to c9atact tre.
?
Yours truly, 0,
oster DOF/ JAB /sw Attachment xc:
M. A. Miller
'R. A. Thomas L. T. Gucwa J. A. Bailey G. Bockhold, Jr.
L. Fowler C. A. Stangler J. E. Joiner, Esquire G. F. Trowbridge, Esquire 88/
4 8412040130 841130 l
PDR ADOCK 05000424 E
ATTACHMENT Listing of open items Item PROPOSED RESPONSE DATE (1)
Design basis temperatures for auxiliary systems 1/31/85 and components (2)
Upgrade of operational meteorological measure-2/28/85 ments program (3)
Foundation competency of clay earl stratum 2/28/85 (4)
Verification FSAR commitments on compaction of 2/28/85 Category 1 backfill (5)
Submittal and evaluation of settlement records 2/28/85 (6)
Foundation design and construction information on 1/31/85 radwaste buildings and tunnels (7)
Bearing capacity stability 12/21/84 (8)
Long-term groundwater and settlement monitoring 1/31/85 requirements (9)
Acceptability of variations in soil dynamic prop-2/28/85 i
erties (10)
Final pipe whip and jet impingement evaluation 3/30/85 l
for high-energy piping.
(11) Clarification of pipe break criteria and pipe 12/21/84 whip restraints (12) Methods to relate measured vibration values to 12/21/84 stress levels (13) Safety-related instrument lines in vibration 12/21/84 l
monitoring program (14) Design of seismic interface anchors 12/21/84 (15) Use of damping values and equivalent static 12/21/84 factors (16) Piping analysis procedures for main steam 12/21/84 and feedwater piping outside containment l
Item (17) Methodology for load combinations 12/21/84 (18)
Piping for service level C and D loadings 12/21/84 (19) Compliance with NUREG-0737, Item II.D.1 12/21/84 (20)
Design of safety and relief valves 12/21/84 (21) Design and construction of component supports 12/21/84 (22) Snubber pre-service examination and 12/21/84 preoperational testing program (23) Preservice and inservice testing of pumps and 12/21/84 valves (24) Acceptable leak rates 12/21/84 (25) Seismic and dynamic equipment qualification 1/31/85 (EQDP i
completed 4/85)
(26)
Pump and valve operability assurance 1/31/85 i
(a) Extent to which standards are used (b) Compliance with RG 1.148 l
(c) Methods and standards for qualification I
(d) Qualification of pump and motor (e) Aging and sequence of environmental condi-tions in maintenance program (f) Pumps affected by static shaft analysis (g) Generic testing criteria for qualifying check valves (h) Administrative control of component quali-fication l
(i) Onsite audit (f) Dependability of containment isolation (purge valves)
(k)
Long-term operability of deep draft pumps j
P Item (27) Sensitivity of CVCS letdown monitor for detecting
' * ' ^ 1/31/85 fuel rod failures (28)
Postirradiation fuel surveillance program addi-2/28/85 tional surveillance (29)
Postirradiation fuel surveillance program disposi-2/28/85 l
tion of failed fuel
.I (30)
Flow measurement capability with crud buildup 2/28/84 (31) Thermal-hydraulic design comparison 12/21/84 (32)
Loose parts monitoring system Closed; see A-10, Q 492.1 (33)
Compliance with NUREG-0737, Item II.F.2 2/28/85 (34) Steamline break DNBR 1/31/85 I
(35) Overpressure protection during low temperature TBD operation (36)
Preservice inspection program 1/31/85 (37)
Impact test data and C, curve for vessel beltline 1/31/85 materials (38) Steam generator tube preservice inspection 1/31/85 (39)
Effect of neutron irradiation damage on limiting TBD weld metal (40) Withdrawal schedules for surveillance specimens 1/31/85 (41)
Pressure-temperature curves to include closure 2/28/85 flange regions (42) Natural circulation boration and cooldown tests 2/28/85 (43)
RHRS operation above 450 psig Closed; see A-10, Q 440.68 (44) Target Rock valves in RVHVS 1/31/85 (45) Compliance with NUREG-0737, Item II.K.1.5 1/31/85 (46) Compliance with NUREG-0737, Item II.K.3.10 1/31/85 l
Item (47) Operator errors during switchover to recirculation Closed; see A-10, Q 440.64 (48) Analysis for large break LOCA with CD = 1.0 Closed; see A-11, Q 440. W (49) Air leakage discrepancy in control room leak rate 1/31/85 (50) Data used to estimate control room dose following 1/31/85 a LOCA (51) Toxic gas evaluation of chemicals 2/28/85 (52) Compliance with RG 1.52 and ANSI 509 1/31/85 (a) No high alarm and trip-alarm signals provided in control room for a temperature sensor located between the heater and first HEPA filter (b) No recorded indication is provided in the control room for the pressure drop across the first HEPA filter (53) Justification for not providing a cooling mech-1/31/85 1
anism for the ESF filtration units (54) Design modification for automatic reactor trip 1/31/85 using shunt coil trip attachment (55)
Level measurement errors resulting from environ-2/28/85 l
mental temperature effects on level instrument reference legs (56) Auxiliary feedwater system 1/31/85 (57) Override of isolation signals Closed; see A-11, Q 420.29, Q420.30 and Q420.41 (58)
Isolators used in the B0P design Closed; see A-11, Q 420.10 (59) Auxiliary relays used with no go tested slave Closed; see A-11, Q 420.15 relays and Q 420.36 (60)
Electrical tunnel ventilation system 1/31/85 (61)
Control room ventilation isolation 1/31/85 (62)
Emergency response capability - RG. 1.97, Rev. 2 Under NRC review
Item (63)
Compliance with NUREG-0737, Item II.D.3 Closed; see A-11, Q 420.8 (64)
Bypass and inoperable status panel-conformance to 1/31/85 Position C.2 of RG 1.47 (65)
IE Bulletin 79-27, Loss of non-class 1E instru-Closed; see A-11, Q 420.2 mentation and control power system bus during operation (66)
Freeze protection for instrumentation sensing and Closed; see A-11, 0 420.11 sampling lines (67)
RCS overpressure protection during low temperature Closed; see A-11, Fig, operation 7.2.1-1 (68)
Compliance with NUREG-0737, Item II.K.3.1 Closed; see A-11, Q 420.55 (69)
Instrumentation for process measurements used for 1/31/85 safety functions (70)
High-energy-line breaks and consequential control 1/31/85 system failures (71)
Control system failure caused by malfunctions of Closed; see A-11, Q 420.6 common power source or instrument line (72)
Compliance with NUREG-0737, Item II.B.3 2/28/85 (a) Criterion 2' (b) Criterion 10 (73)
Fire hazards analysis 2/28/85 (74)
Fire doors 2/28/85 (75)
Fire dampers 2/28/85 (76) Soundproofing materials 2/28/85 (77)
Safe shutdown 2/28/85 (78) Alternate shutdown 2/28/85 (79)
Power supplies for ventilation 2/28/85
(80)
Fire detection 2/28/85 (81) Valve supervision 2/28/85 (82)
Automatic sprinkler systems 2/28/85 (83)
Standpipes 2/28/85 (84) Halon 1301 systems 2/28/85 (85) Control room complex 2/28/85 (86) Secondary water chemistry monitoring and control 2/28/85 program (a) Sampling schedule and control limits (b)
Procedures (c) Sampling points (d) Data management (e)
Responsible authority (87) Quality assurance for main condenser evacuation 2/28/85 system l
(88) Quality assurance for turbine gland sealing system 2/28/85 i
(89) Volume reduction system Under NRC review (90)
Initial training program 2/28/85 (a) Simulator training (b) Walkthrough training (c)
Review and audit (d) Description of SRO training (e) Description of training program for heat transfer, fluid flow and thermodynamics (f) Training complete before preop tests begin (g) Numbers of personnel for whom training and licensing is planned to meet Tech Specs I
Item e
(91)
Licensed operator requalification training program 2/28/85 (a)
Implementation schedule (b) Procedures for record retention (c)
Lack of heat transfer, fluid flow and thermo-dynamic training (d) Training for mitigating core damage (e)
Review of abnormal and emergency procedures (92) Compliance with NUREG-0737, Item I.A.2.1 2/28/85 (a)
Lack of heat transfer, fluid flow, and thermo-dynamic training (b) Ratesting of simulator response 1
(93) Compliance with NUREG-0737, Item I.A.2.3 2/28/85 (94) Compliance with NUREG-0737, Item II.B.4 2/28/85 (95) Training for nonlicensed plant staff 2/28/85 (a) Organization teaching the course (b) Distribution of training (c) Health physics training for mechanical and electrical maintenance personnel (d)
Refresher instruction (e) Schedule (f) Number of personnel for whom training is l
planned to meet Tech Specs (96)
Fire protection training 2/28/85 (a) Fire fighting plan (b) Content of instruction as par BTP CMEB 9.5-1 (e.g., meetings every 3 months, drills, refresher training)
Item (96)
Fire
- protection training (continued) 2/28/85 (c) Qualified individuals as instructors (d) Training for other plant employees (97)
Shift technical. advisor training 2/28/85 (a) Mitigating core damage (b) INPO recommendations (98)
Procedures generation package 1/31/85 (a) Plant-specific technical guideline (b) Writer's guide (c) Validation and verification programs l
(d) Training program description (99)
Initial test program 2/28/85 l
(100) Technical Specifications to require four valves 2/28/85 to be closed during refueling (101) Inadvertent boron dilution during modes 3, 4, 1/31/85 and 5 (102) Compliance with NUREG-0737, 2/28/85 Items II.K.3.1/II.K.3.2 (103)
Radiological consequences of SGTR 2/28/85 (104) Operator action in event of steam generator tube 2/28/85 rupture (105) Compliance with regulatory guides 2/28/85 (106) Operational QA program 2/28/85 (107) Detailed control room design review 3/1/86 (108) Safety parameter display system 9/1/85 l
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