ML19221A594
| ML19221A594 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/10/1979 |
| From: | Telford J Office of Nuclear Reactor Regulation |
| To: | Grimes B, Stello V, Vollmer R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7905230278 | |
| Download: ML19221A594 (11) | |
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April 10, 1979 NOTE TO:
V. Stello R. Vollmer B. Grimes R. Mattson FROM:
T. Telford The attached tables are designed to assure follow-up of the licensees priority actions by NRC.
In this first draft we have collated the various lists used by the licensee management and scheduling committee and assigned them to lead NRR management people.
The next step is for the lead managers to delegate the important tasks to NRC personnel at the site or in Bethesda, as appropriate, and to provide me with a less than one page des-cription of each item including schedule information and respon-sible individuals in NRC, GPU/ Meted, and the appropriate supplier organization.
I will be providing you with the standard fo.m for these purposes on 4/10 AM.
aka4 Tom Telford
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CRIMES' LIST 1.
Install Aux. Building - FHB Off Gas Filter System in new structure outside Aux. Building.
Tie into Aux. & FHB ventilation system.
2.
CAP-C011 processing system to be available Thursday.
3 Identify storage required for liquid waste.
4.
Process Unit I and 2 Low Level Liquid through Cap-Gun.
5 Change Existing Auxiliary Building Filters.
6.
AB/FH Filter - Preliminary Design Staging Steel Foundation Duct Filter / Fan 7
Prima ry wa ter into Auxiliary Building 8.
Determine source of high lodine-AB elevator.
9 Arrange MSA to test new filters - (DOP test).
10.
Review ventilation effects when FH o/s door is opened - also survey request by HP.
11.
Determine Leakage Paths f rom Unit 2 to Unit 1.
W 12.
D/C Liquid aste Processing System Long Term.
13 D/C Emergency RB Gas Purge Clean-Up System.
14.
Preheaters to FHB Vent Filters 15.
Develop Vaste Management Gam Plan - Long Term.
16.
Sanple AB/FH Bldg. for filter replacement indicating acceptable operation.
17 Determine disposition of water:
short term medium term 18.
Determine sources of leakage to environment.
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Grimes' List (Cont ' d) s 19 Design waste gas system for pump down of RB to fuel pool.
20.
Review fire protection for charcoal filter.
e 165 193 4
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2 VOLLMER'S LIST 1.
Provide a sensor for steam generato and pressurizer level that does not rely on any electrical cor:ponents nside the containment building.
The rensor shall monitor water level over as wide a range as is practical.
The sensor cha!1 have suf ficient accuracy to monitor level trends and changes in level greater than 24 inches.
2.
Design a plant modification to monitor containment water level.
The sensor shall have a wide range and narrow range band of indi-cation as follows:
Narrow Range:
l' - 4.5'
+1" Vide Range:
l' - 30'
+1' The design shall not rely on any electrical components located in-side the Reactor Building.
The amount of water from containment that is allowed to fill piping outside containment shall be mini-nized or eliminated.
3 De"elop liquid waste transfer procedure.
Modify currently available one IF possible.
- preferred method:
containmei.* sump directly to Aux. Bldg.
sump tank.
- Stop at 2 R/Hr. in piping; re-evaluate.
4.
NRC release needed on increase in boron concentration.
5.
Plant Ops needs the following support from B&W:
a)
Procedure for what to do if we lose Icvel ind i ca t ion.
in "A" S.G.
b) What action should be taken regarding make-up tc "B" generator.
Site has procedure transmitters on way.
6.
Provide Bob Arnold with history of samplirg secondary side of "B" generator by 2200.
165 194
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2 y0LLMER' S L I S'." (Con t ' d) 7 Develop Procedure to measure gas level by MU Tank Pressure.
8.
Update emergency plan.
9.
Provide list of bypassed interlocks.
10.
Calibrate Heise Gauge - Delta P pressurizer level.
11.
Draw pressurized and degassed primary samples.
12.
Provide minimum allowable RCS pressure for degassing.
13 What action should be taken rega rding make-up to B Generator.
14.
Analysis of what gas conen. in primary should be.
15 Depressurize 16.
Return to 1000 PSI 17.
Measure Gas Level via '
- e-Up Tank Pressure Based on TS Procedure.
18.
Reactor Cooldown to 220 F.
Steaming 19 Calib. Gauge /obtain Coolant sample 20.
Obtain Sample of Unit 2 Liquid Waste Tanks 21.
Restore Pressurizer Heaters 22.
Repair Fitting on Makeup Tank to Reactor Building 23 Install new Vent Stack Monitor 24 Install Main Cond. Vac. Pump Filters 25.
Recommend i f Pri. sample worth exposure 26.
Increase Letdown flow 2/.
Provide degeneration procedures:
A.
Fire in Containment B.
Fire in Auxiliary J.
Fire in other areas D.
Evacuation of control room E.
Breach of waste systems e
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3 VOLLMER' S LI ST (Cont ' d) 28.
Updated plan for emergency transfer to natural circulation.
29.
Receive and disseminate reduced plant data.
30.
Fire in plant areas procedure.
31.
Evacuation of Control Room procedure.
32.
Procedure for loss of SG heat sink - short term.
33 Procedure for determining gas level in RCS by M/V tank pressure increase.
34.
Reduce water level in Reactor Building - Criteria.
- 35. Veri fy let-down valve alignment of make-up system.
36.
Ensure tagging and valve positioning to maintain containment integrity.
37.
Calculat9 cue le release parameters to ensure acceptable limits.
Prepare sample procedure for air / liquid release rates - in/out plant.
38.
Establish spill ctri. procedure Provide organization set-up on Turb. Bldg. Operating floor.
Get Geli set-up at south bridge.
39 Tank inventory Status.
40.
Flush System for AB Components 41.
Organize an Integrated QA'd Radiation Survey.
42.
Obtain water sample from Unit 2 Containment Sump - Procedure.
43 Prepare contingency plan for Di rect Water Trans fer f rom U-2 to Fuel Pool - Procedure for pumping.
2 t
4 VOL LMER's LI ST (Cont 'd) 6 3
44.
Develop method for flooding containment with 10 ft of water.
45.
Design temporary shielding covers for DHR pits.
46.
Evaluate line-up to use one decay heat and one spray pump.
47 Containment vent stack monitor HPR-219 recovery system.
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MATTSON' S L I ST l.
Develop complete package for secondary side cooling of Steam Gene rator "B".
2.
Design / Install.
System for pressure control (including makeup) of reactor coolant system.
3 Design, fabricate, procure, erect, and Install an aircraf t hardened, leak proof shielded structure to house two (2) long term high cressure decay heat removal systems.
4 Develop Electrical Distribution System.
Install cabling and switchgear from the 2-2500 kW 4160V diesel generators to current BOP loads now requiring loss of offsite power protection.
5.
Install storage vessels in the fuel storage pool of Unit 2 (Pool "A").
Provide a method to move equipment, tanks, etc., into the fuel handling building without unacceptable loss of containment.
6.
Provide a design change to the elec.trical supply for the pressurizer heaters that provide the capability to isolate grounded heaters.
The derign shall provide the capability to recover as many un-grounded pressurizer heaters as possible.
7 Design a new Instrument air supply that provides redundancy for the existing instrument air system and is not af fected by loss of of f-s i te powe r.
8.
Provide a design for short-term cooling via the decay heat drop-line through new pumps and heat exchangers.
The new equipment shall be located in the Fuel Handling Building in order to mini-mize radiation levels in the Auxiliary Building.
The new equip-ment shall provide redundancy for the existing decay heat system.
The new piping tie-ins shall also incorporate connections to be utilized at a later date for a long-term forced flow decay heat sys tem const ructed adjacent to the Fuel Handling Building and Diesel Generator Building.
9.
List of critical systems for pre <ent condition.
10.
Analysis of In-core thermocouples during LOF on 4/6.
11.
Previde stress analysis for generator (Point B to C).
L-2 MATTSON' S L I ST (Con t ' d) 12.
Renove Unit 2 Fuel Racks 13 Install Diesel Driven Inst. Air Comp.
14.
Corg Analysis __
15.
Boron Concentrations 16.
Provide recommendation for alternative methods of P/V control.
17 Evaluate need for backup HPl pump (Hydrolaser).
18.
Provide estimate of required HPl fl ow for 200 to 2500 psi (degener-ated state).
19 MPR analysis of water hammer.
20.
Procedure for taking "A" S/B solid.
21.
Analysis of solid secondary problems.
22.
"B SG Closed Cooling System.
Criteria / approval (P.B.8.a.)
23 Back-up Reactor Pressure Control System (a c t i ve).
Criteria /
approval (P. B.4. ) (P. C.4. ).
24 Provide criteria for determining if natural circulation is not achieved from results of instrumentation.
25 Additive to Primary Water - Long Term.
26.
Design Shield Wall at condensate demineralizers - Long Term.
27.
Provide I page description of each Plt Mod.
28.
Recommend methods to improve reliability o' implant electrical supply.
29 Develop package for secondary side cooling of 5/GB.
30.
Develop package for use of secor.dary services cooler.
31.
Design / install system for pressure make-up control of RCS.
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MATTSDN' S L I ST (Cont ' d) 32.
Review B&V natural circulation cooldown proc.
33 Provide electrical power supply for corss connecting RB with FHB purge filters.
34 Design supports for Cond. H line to surface condenser H hot CO-C-IB to make it as seismically capable as feasible.
35.
Examine IE diesel generator to determine if BOP loads can be added.
36.
Review alternate cooling source for secondary.
37.
Supports for M.S. sy: tem in Turbine bldg. when filled (related to #52).
38.
Location for secondary plant diesel.
39.
Max P&T for DHR downstream of Valve DH-V3 40.
Back-up Power Source for secondary plant loads.
41.
Augment instrument. air system (design).
Procute/ erect augmented instrument air system.
42.
Design / install aircraft hardened decay heat system housing.
43.
Develop Electrical Distribution System.
Install cable / switch-gear (2) 2500 kV diesel generators.
44 Determine decrease in structural margin for the Aux. Bldg.
(Ai rcra f t impact).
45.
Provide minimum allowable RCS pressure fcr degassing.
46.
Determine minimum primary system pressure (point D, Base Plan).
47 Document of sequence of Plant conditions in base plan.
48.
Design a passive head system which will be in place by April 14, 1979.
49.
Design active pressure control system.
50.
Coordinate National Lab work support of NRR work at TMI-2 site.
Assigned to V.
Sixby, INEL.
165 200
STELLO* S Ll ST I.
Reconstruct ion of event.
s 165 201