ML19322D580
| ML19322D580 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/09/1979 |
| From: | Herbein J METROPOLITAN EDISON CO. |
| To: | Rogovin M NRC - NRC THREE MILE ISLAND TASK FORCE |
| References | |
| TASK-TF, TASK-TMR 790626-01, 790626-1, NUDOCS 8002180003 | |
| Download: ML19322D580 (15) | |
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- f fJ Post Of fice Box 542 M h_;.-LL-web -l M Nedl Reading Pennsylvania 19640 215 929-3601 Ybiter's Direct Dial Number 4
July 9, 1979 l
NRC/TMI Special Inquiry Group j
Attn:
Mitchell Rogovin, Director U.S. Nuclear Regulatory Agency Washington, D.C.
20555
Dear Mr. Rogovin:
4 Ref:
NTFTM 790626-01 t
Enclosed please find a partial response to the question enclosed with your letter to me of June 26, 1979. Responses to the remaining sections of the question will be sent by July 13, 1979.
- ncerely, 1
J. G. Herbein Vice President-G< ' ration i
JGH:LWH:dr Enclosures cc:
E. Blake 1
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f.'etropoStan Ed son Company is a f/ ember of the Geneal Pub;c U:tt.es System p
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ENCLOSURE 1 List of Reques t_ed Inforria t ion 1.
a.
Provide status of Unit 2 on March 27 and 28, 1979.
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(1) March 27 Three Mile Island Unit Two was a t 97% powe r (8 72 M'n'e) with the Integrated Control System in full automatic.
Eod groups one thru five were fully withdrawn, rod groups six and seven were 95% withdrawn and rod group eight was 27% withdrawn.
Reactor Coolant System total flow was approximately 138 million pounds per hour flow,and the Reactor Coolant System pressure was 2155 psig. Reactor Coolant System average temperature was 582 F, and the boron concentration was 1027 ppe.
The gross beta / gamma reading for the primary coolant was.3783 uci/ml and j
the primary leakage rate was.4 gpm.
The average core burn up was 93 EFPD.
(2) March 28 Conditions in the primary remained very much the same a s ab ov e un t il 4 : 00 a.m. on Ib rch 28.
At tha t time the following conditions in the secondary existed:
Steam Generator A Steam Generator B Loop Feedwater 5.7459 MPPH*
5.7003 MPPH*
Operating Level 56%
57.4%
Startup Level 158.8 inches 163 4 inches Steam Pressure 910 psig 889.6 psig Feedwa ter Temperature 462.7 F 462.7 F Steam Temperature 595 F 594 F
- MPPil - Million Pounds Fer Hour
- Steam Generator Feedwa ter Pumps (FW-P-1 A and FW-P-1B) were in service, 1 Condensate Eooster Pumps (CO-P-2A, CO-P-2B and CO-P-2C) were in service, and Condensate Pumps (CO-P-1A and CO-P-1B) were in service.
Reactor Coolant Makeup Pump B (MU-P-1B) was in service supplying makeup and Reactor Coolant Pump Seal injection flow. Normal Reactor Coolant System letdown flow was approximately 70 gpm.
The Reactor Coolant System boron concentration was approxinately 1030 parts per million. The Pressurizer Spray Valve (RC-V1) and the pressurizer heaters were in manual control while spraying the pressurizer to equalize boron concentrations between the pressurizer and the remainder of the Reactor Coolant System. The pressurizer safety valves discharge header thermocouples were in the range of 190 F due to leakage thru one of the Pressurizer Safety Valves (RC-RIA and RC-RIB).
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Equipment out of service on March 27 and 28,1979 2
(1)
Chlorine Evaporator (CL-2-1?
(2) Condensate Flow Transmitter (CO-FT-070) i
.(3)
Clearwell Tank (WT-T-2) i (4) Mechanical Room Fan Coil Unit (AH-C-24)
(5)
Soiled Exhaust Prc-filter ( AH-F-27)
(6)
Feedwater Heater 3A Sight Glass (7) Temporary Sodium Hydroxide Pump (WT Caustic Tank)
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(8) Heater Drain Pump B (HD-P-1B)
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(9) Reactor Building Normal Cooling (RB-21A-2) j (10) Heater Drain Valve (HD-V-65B)
(11) Control Building Fan Coil Unit (AH-C-52B HTR) i (12) Control Building Fan Coil Unit (AH-C-52D) l 1
(13) Evaporative Cooler (RB-L-183)
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(14) Mechanical Draf t Cooling Tower Fan 2-3 4
(15) tbke Up Skid Acid Block and Bleed Valves (R8, 9 & 10)
I (16) Heater Drain Limit Switch (HD-LS-327) on Heater Drain Tank (HG-T-1)
H (17) thin Stream Thermostat (MS-U35B) on Turbine Bypass Line i
j (18) Reactor Coolant Hot Leg Drain (RC-U-4) i i
(19) Fire Door Between Auxiliary and Fuel Storage Building (20) Ammonia Pump A (AM-P-1A)
(21) Breaker 24 (spare) 2-4V vital power supply (22) Auxiliary building sump tank (WDL-T-5)
(23) Sodium Thiosulfate Tank (DH-T-3)
'(24) FMke Up System Pressure Transmitter (MU-2-PT)
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.curveillance Testing in Progress
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To be supplied at a later date 1
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Limiting Plant Conditions on March 27 and !' arch 28, 1979 To be supplied at a later date i
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Procedures being revised as of I: arch 28, 1979 See Enclosure 2 " Procedure Change Requests"
- " Temporary Change I otices" Enclecure 4 " Unit 2 Procedure Index"
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Pending Regulatory Action as of Fbrch 28, 1979
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The following Technical Specification Change Requests (TSCR) l f
j had been submitted, and were being reviewed by NRC:
a)
TSCR #003 re:
the adequacy of patrolling fire watches vs.
4-continuous watches b)
TSCR #006 re: misc. changes to the administration section of n!I-2 Technical Specifications c)
TSCR #016 re: defeating fast transfer of Station BOP loads I
upon the failure of an aux. transformer i
d)
TSCR #17 re:
operability of control rod reed switch position i
indicator channels d)
TSCR #20 re:
minimum number of incore detectors needed for f.
quadrant power tilt measurements e)
TSCR #10 re:
f requency for performing heat balances In addition, NRC was reviewing Met Ed submittals regarding Met Ed's proposed course of action in several areas. Many of these proposals were made in~ response to MRC requests for action in the i
affected area. These areas include the following:
1)
Reactor Bldg. Purge Value Analysis NRC request:
11/29/78 Met-Ed Response: 3/16/79 i
2)
Single Auxiliary Transformer ~peration NRC request: 8/18/78 Met-Ed Response:
8/29/78 4
j (verbal)
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3)
ISI Program Met-Ed Submittal:
7/25/79
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(Continued)
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NRC Intpection Report Open Item List Insp. Rpt. No.
Subject 78-10-03 ANSI N45.2 9 78-16-01 TLD Performance vs ANSI Standards 78-16-02 Re-evaluate FM of Air Sampling Units 78-16-03 AT Instrument Calibration Data 78-16-04 Settling Basins For Yard Drains 78-29-01 Test Procedure 600 5 PR 2700 78-30-01 AR Setpoints vs Tech Spec 78-32-02 Test Procedures 800/11 & 800/31 78-32-03 Test Procedures 800/35, 800/5, 800/18 800/36, SP 800/8, 80023, 800/2, 800/12 and 800/22 78-32-05 AP 1013 Temporary !!echanical Modification 78-32-08 PAI 2 78-033 78-31-04 Survey Top of Reactor Bldg Before Allow Access 78-36-01 Improperly and/or Inadequate Completed OP procedures 78-36-02 Annotations other than TCN's - Not Acceptable 78-36-03 2301-S1 Not Properly Implemented 78-36-04 2301-M4 Needs Revision 78-36-05 2303-M13 and 2102-4.1 Need Revision Reactor Bldg Purge Time Tracking 78-36-06 Deficiency - Value verification not performed as required
1f. -(Continued)
NRC Inspection Report Open. Item List Insp. Rpt. No.
Subject
- 78-37-04 Check Valve Testing - Review Procedures 78-37-05 Fail - Safe Actuations - Put in Procedures 78-37-01' Revise Reactor Coolant Pump Procedure
'78-37 Snubber Maintenance Procedure 78-37-03 Snubber Seal Material Verification 78-39-01' Verify Acceptance Criteria k'as Met on Data From Generator Trip Test 78-39-01 Solder Iron and Cardboard Boxes in Cable Room.
78-38-02 3303-M1 Manual Pushbutton didn't start diesel 78-38-03 Sealed Beam Emergency Light Mislocated 79-01-01 LER 78-67/3L Battery Changes Blown Fuses 79-01-02 LER 78-68/3L Diesel Generator Exceeded Allowable Valve 79-01-01 Biological Shield Surveys - Neutron Shield Tank 79-04-02 Entering High Neutron Dose Area without continually monitoring 79-07-01 LER 78-74/3L and LER 79-04/3L 79-07-02 LER 78-05/3L A/E Evaluatien and PORC Review of Results
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79-07-03 Revise LER 79-10/1T
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Status of Pertinent Commitments to the Regulatory Staf f
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.(1) Environmental Oualification of Electrical Components 9
- Review was completed prior to 3/27/79, response was being prepared for submittal to NRC.
i (2) ~Small Break LOCA Piping, Cross - Connec,t Design had been approved by NRC (12/8/78)
Work was progressing toward installation at the first scheduled refueling outage.
i (3) Feedwater Isolation Valves Work was progressing toward installation at the first refueling outage.
Specifically, analyses were being performed to demon-strate design adequacy.
NRC had perforced a preliminary design review and had approved the design concept, but had l
l-I requested the above-mentioned analyses prior to issuing a
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formal design acceptance.
(4) Aysemetric LOCA Loads Work was progressing toward completion of the analysis in June l
of 1980. B & W analysis of cavity loadings and vessel /
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vessel internals loading was in progress.
(5) Appendix I Tech Specs Working on draf t submittal due to NRC on 4/15/79 (since revised f
to 7/15/79)
(6)
IE Bulletins:
i 79-C2 - Pipe Support Base Plates (issued 3/8/79) i l
79 Longitudinal Pipe Welds (issued 3/13/79) i Work was underway to investigate the applicability of concerns raised in these bulletins for TMI-1 and/or TMI-2.
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Concerning IE Bulletin 79-02, the architect engineering firm 'for 'each. unit had been instructed to investigate the extent'to'which the Bulletin applied to each unit. This investigation was underway but had.not been completed.-
k-Concerning IE Bulletin 79-03, it had been determined that i
the Bulletin was not applicable to TMI-2, but the investigation for applicability for TMI-1 had not yet been completed.
(7) Security 4
The TMI Security Plan had been approved. Work was underway to implement some security systems. However, NRC approved compensatory actions were in effect.
(8) License Conditions i
Operating License No. DPR-73 stipulated that certain items 3-should be completed within an allotted time frame.- A number of these items had been completed prior to 3/27/79 Work was I
continuing on the remaining items. Those items which had not yet been completed were as follows:
2.c.3.g.1 2.c.3.g.2 F.1 1
2.c. 3.g.3 2.c.3.h 2.c.3 1 -
2.c. 3j 2.c.3.k 2.c.3 1 6 2.c.3 1.7-2.d 2.e.1 2.f.
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... l.h ' All connections and shared activities between TMI-l and 2.
(1) Shared Activities j
_ Security - Common site protection force and protected area.
Fire Suppression Water System - Common system for both Unit I and Unit 2 Radwaste - Solid - Radwaste solidification done in Unit 1 Industrial Waste Treatment System -
L Paging System - Common page system - can be isolated 230~ KV Substation - of fsite power for both Units provided via common 230 KV substation River Water-Chlorinator - Common system to chlorinate each unit's river. water cooling system.
Meteorological Tower - Common tower reading out in each unit's control room River Water Discharge Canal - Common discharge to river from each unit's mechanical draft cooling tower 1
Primary Sampling Room - Common room for sampling Unit I and Unit 2 primary samples.
(2) Connections Extraction Steam System - Either unit can supply other unit with extraction heating f
Demineralized Water System (Supplied by Unit 1) 1 j
Condensate Return System Condensate return connection if extraction j
steam is supplied 1
Turbine tube Oil Storage-System - Common storage and makeup capability I.
Radwaste Liquid - System - cross-connected to transfer liquids between the units ii Instrument Air System - (not normally open)
Domestic Water System - (supplied by Unit 1)
HVAC Fuel Handling Building - common bldg each with its own Heating, j
Ventilation & Air Conditioning On Parch 28,.1979 extraction stream was being supplied by Unit 2 to Unit 1, Demineralized Water was being supplied by Unit 1 to Unit 2, and Condensate Return System was being supplied by Unit I to Unit 2.
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FSCLOSURE 2 s
l Procedure Change Jequests (PCR)
PCR No.
Procedure No.
2-78-241 2104-4-3 cj 2-78-429 2104-4-3 2-78-609 2401-7-1 2-78-610 2401-5-3 2-78-685 2401-4-1 2-78-686.
2401-4-2 2-78-687 2401-2-4 2-78-688 2401-2-1 2-78-689 2401-4-3 2-78-690 2401-4-4 2-78-932 1420-4-10 2-79-004 1621-2 2-79-014 2104-4-2 2-79-024 2303-M14A-E 2-79-025 2303-M2A/B I
2-79-030 2303-M24A/B 2-79-032 2303-M31A-D
.2-79-037 2303-Q7 2-79-043 1430-SPDN4 2-79-047 2303-M14A-E 2-79-055 2303-M31A-D 2-79-059 2204-18.A5,A6,C5,D6 2-79-073 2134-3-7 2-79-078-2305-RS 2-79-082 2106-3-1 4
2-79-087 2311-Fi 2-79-088 2103-1-9 2-79-089 2311-F2 2-79-090 2311-1 2-79-091 2204-8.A23 2-79-092 2302-Rl-2 2-79-093 2302-Q1 2-79-094 2104-4.4 2-79-095 2104-1-5 2-79-096 2104-2-2 2-79-097 2302-R1-5 2-79-098 2602-R10 2-79-099 2602-R-1 2-79-100 2106-2-1 2-79-101 2106-2-4 2-79-102 2106-1-4 2-79-103-2106-1-2 2-79-104 2104-2-2 2-79-105 2104-2-11 2-79-106 2106-2-1 2-79-107 2311-6 2-79-108 2303-M6 i
2-79-109 2302-Rll 2-79-110 2101-1-1 2-79-111 2103-1-1 2-79-112 2104-1-2 4
2-79-113 2103-1-2 2-79-114 2104-3-7 2-79-115 2301-51 2-79-116 2302-5Al
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FNCLOSURE 3 Temporary Chanre'Not.ites (TCN) 5-ygg No.
Procedure No.
1 2-79-001 1021 2-79-002
' 2303-M2 A/B 2-79-003 2303-M24 A/B 2-79-009 1630-2 2-79-011 2303-M31A-D 2-79-015 2303-M21 2-79-021 2104-4-2 2-79-023 2313-R7 2-79-026 1621-2 2-79-027 ~
2106-1-2 2-79-028 2104-4-3
'2-79-030 2301-51 2-79-034 2303-M2 A/B 2-79-035 2303-M29 A/B 2-79-037
-2301-M12 2-79-039 2104-4-2 2-79-042 2303-M14 A-E 2-79-044 3303-Al 4
2-79-050 2303-Q5 2-79-054 2204-8-A23 2-79-055 2302-Rl-2 2
2-79-056 2302-Q1 2-79-057 1622-02 2-79-058 2106-3-1 2-79-059 2303-M14 2-79-061 2303-Q5 2-79-062 2301-M3 2-79-063 2303-M2 A/B 2-79-064 2303-M32 A/B 2-79-065 2104-4.2
'2-79-066 3301-M1 2-79-067 1005-11 2-79-068 1622-2301 2-79-070 2301-3015 2-79-072 2302-Rl-5 2-79-073 2602-R102 79-074 2103-1-2 2-79-075 2302-Rll 2-79-076 2303-M6 2-79-077 2311-6.11 2-79-078 2104-2-11 2-79-079 2202-2-3 2-79-080 2106-3-2 2-79-081 2623-R2
- 2-79-082 2102-3 1
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