ML19263F012
| ML19263F012 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/27/1979 |
| From: | Krauss R GH-BETTIS CORP. |
| To: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| REF-PT21-79-113-003 NUDOCS 7910240456 | |
| Download: ML19263F012 (4) | |
Text
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ATTACED IS A PART 21 REPORT FROM IE F%ll1 NIT - R0W 359E/W PART 21 IDBfTIFICATION fD, 79- //3-o o 1 COMPANV t#E C,d /3&'
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DATE OF LETTER 47/ 79 DOCE.T NO, So ~32a-8 DATE DISTRIBllTED %/m ORIGINAL REFORT SUPPLEFENTARY X DISTRIPUTION:
REACTOR (R) l' FUELCYCLE&
SAFEGUARDS (S)
VATERIALS(M)
NRR/ DOR, DIRECTOR AD/FFFEI AD/SG-IE NRR/DPM DIRECTOR RES/FCMS AD/RDI AD/ROI(2)
REGIWS REGIONS AD/RCI IEFILES NRR/DDR,DIPECTOR PEGIONS PDR NES/SG SS-881 IE FILES (2)
LPDR PDR CENTRAL FILES CENTPAL FIIIS-SS-396 LPDR CENTPAL FILES (CHRON)
CByFILES(CHRON)
TEPA IE FILES (2)
~LPDR CBfTPAL FILES 016 TEPA B03DBiNIG,MPA CBM FILES (CHRM)
BGBDB4NIG,FvA CENTPAL FILES - SS-396 ACTION:
B03DBlNIG,f'PA PRELIMINARY tMTION OF THE ATTACHED REPORT INDICATES LEAD RESPONSIBILIT FOLLOW-UP AS SH0hN BELGi:
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DIRECTOR, REGION IV OFFICE OF INSPECTION AND ENFORCEM'NT U. S. NUCLEAR REGULATORY COMMISSION 611 RHINE PLAZA DRIVE,. SUITE 1000 ARLINGTON, TEXAS 76012
SUBJECT:
POTENTIAL DEFECT REPORTING UNDER 10CFR, PART 21, SECTION 20o OF ENERGY REORGANIZATION ACT REF:
METROPOLITAN EDISON COMPANY 3 MILE ISLAND UNIT NO. 2 Gentlemen:
This letter, in triplicate, supplements and amends our report submitted to the Nuclear Regulatory Commission, Region IV office dated April 11_, 1979.
The information in this submittal is the result of searching both GH-Bettis and Henry Pratt Company files through the current date.
The attached listing shows all the ASCO solenoid valves which have been furnished as accessories on GH-Bettis actuators mounted on Henry Pratt Company butterfly valves supplied to nuclear power plants for containment or related service in which the environmenta conditions may exceed the ratings for the solenoid valve plastic parts.
For corrective action the Henry Pratt Company is notifying all power plants listed by September 15, 1979 of the potential defect for the review and evaluation as related to the safety impact.
This notification will also include information about currently available qualified solenoid valves which the power plants may use in taking any necessary corrective action.
Sincerely, k f he
R. W.
Krauss, P. E.
Vice President, Engineering RWK/cck 2220 053
Page 1 of 3 PROJECTS AND EQUIPMENT August 14, 1979 Pratt Order Utfif ty &
Valve Size Solenoid Item #
Project
& Hodel Model F Valve Tag Numbers 7-4112-182 Metropolitan Edison
- 36" NRIA ASCO All-V2A Three Mile Island #2 HT8331A45 Aft-V2B AH-V3A All-V3B 7-3661-1 Arkansas Power & Light Company 54" NRIA ASCO CV-7401 Arkansas Nuclear #1 8316B15 CY-7402 or 8316C35 7-4019-1 Wisconsin Public Service 36" NRIA ASCO CV-31i.3 Kewaunee #1 & 2 8331A45 CV-31124 8316D15 CV-31125 CV-31126 7-4091-1 Northern States Power 36" NRIA ASCO Unit 1 Unit 2 (Unit 1)
Prairie Island #1 & 2 ilT8331A45 CV-31212 CV-31316 7-4092-1 CV-31213 CV-31317 (Unit 2)
CV-31569 CV-31574 CV-31570 CV-31575 7-4054-182 Baltimore Gas & Electric 48" NRIA ASCO Unit 1 Unit 2 Calvert Cliffs #1 & 2 FT8331A45 N012-1-CV-1411 4022'2-CV-1411 N012-1-CV-1413 H022-2-CV-1413 N011-1-CV-1410 N021-2-CV-1410 N011-1-CV-1412 N021-2-CV-1412 7-3915-1 Florida Power Cor? oration 48" NRIA ASCO AHV-1A
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Crystal River #3 8331A29 AHV-10 rs)
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CD Valves referred to in original report dated 4-10-79 c:a
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.Fage 2 of 3 August. 14, 1979 Pratt Ordr Utility &
Valve Size Sole %1d item i Project
& Model Model i Valve Tag Ntsnbers D-0067-3 Alabama Power Company 8" HRS ASCO Unit 1 Unit _2 (Unit 1)
Farley Nuclear #1 & 2 HT8316015 MK284-14 !!K2-44-8 D-0067-4 (4)
(4)
(Unit 2)
D-0067-5 Alabama Power Company 18" NRS ASCO Unit 1 Unit 2_
(Unit 182)
Farley Nuclear il & 2 HT8316815 Q1P13V289 Q2P13V289 Q1P13V290 Q2P13V290 QlP13V291 Q2P13Y291 Q1P13V292 Q2P13V292 N6903-1 Northern States Power 18" 2FIl ASCO Unit 1 Unit 2 (Unit 1)
Prairie Island #1 & 2 8316B15 CV-31633 CV-31635 N6904-1 CV-31634 CV-31636 (Unit 2)
CV-31622 CV-31314 CV-31310 CV-31315 D-0029-2 Mississippi Power & Light 20" NRS ASCO Tag Prefix: SQ-20-HBC-BF-A0 Grand Gulf #1 & 2 T8321A6 Untt 1 Unit 2 T011U F0110 F012L F012L F013L F013L N
F015L F015L N
F016L F016L N
F017L F017L O
F034U F034U 00350 F035U a
Ln D-0072-2 Hississippi Power & Light 6" MRS ASCO Tag Prefix: SQ-6-IIBB-BF-A0 Grand Gulf #1 & 2 IIT8321A6 Unit 1 Unit 1 F009-LOWY F057-LOWY
Page 3 of 3 August 14, 1979 Pratt Order Utility &
Valve Size Solenoid Item i _
Project
& Model Hodel i falve Tag Haubers 0-0072-3 Hississippi Power & Light 8" NRS ASCO Tag Prefix: SQ-8-HBB-BF-A0 Grand Gulf fl & 2 HT8321A6 Unit 1 F007-LOPtG 0-0072-5 Hississippi Power & Light 6" HRS ASCO Tag Prefix: SQ-6-lib 8-BF-A0 Grand Gulf #1 & 2 IIT8321A6 Unit l_
Unit 1 F056-LOPHY F010-LOPHY D-0083-1&2 Hississippi Power & Light 6" NRS ASCO Tag Prefix: SQ-6-llBB-BF-A0 Grand Gu'.f il 8 2 HT8321A6 Unit 2-Item 1 Unit 2-Item 2 F009-LOWY F010-LOPWY F057-LOWY F056-LOPWY D-0083-4 Hississippi Power & Light 8" NRS ASCO Tag Prefix: SQ-8-HBB-RF-A0 Grand Gulf #1 & '
IIT8321A6 Unit 2 F007-LOPWY 7-3794-1 Comonwealth Edison 42" RIA8 ASCO Unit 1 Unit 2 Zion #1 & 2 HTT8316C34 1ADV-RV0001 2A0V-RV0001 1A0V-RV0002 2A0V-RV0002 IA0V-RV0003 2A0V-RV0003 1A0V-RV0004 2A0V-RV0004 4
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MEMORANDUM FOR: Karl Kniel, Chief, Core Performance Branch, DSS THRU:
Daniel Fieno, Leader, Reactor Physics Section, CPB/ DSS.h FROM:
Mary Dunenfeld, Reactor Physics Section, DPB/ DSS
SUBJECT:
BNL-OSS PHYSICS TECHMICAL ASSISTANCE MEETING ON AUGUST 30, 1979 M. Dunenfeld visited BNL on August 30, 1979 to discuss progress on the DSS Physics Technical Assistance Program. r J. Carew reported the results of analysis of the TMI-2 source range detector response. We have been attempting to calculate the large variation in source rance detector response observed durir.g the early cart of the TMI-2 accident. The results indicate the sensitive factor is voiding in the downcomer recian of the reactor. A report is available (addressed to D. Fieno, fra J. Carew, dated August 28, 1979) "or anyone interested in further detai!s of this work,.
D. Diaa nd reported the pronress made by S. Cheng on analyses being cerfomed with ME"Ih. A recort is beine written covering the CHR calculations and the rod ejection calculations perfomed by J. 'lerczia before he left BNL. The BM rod drop calculations are not ouite comolete, as another case is in preoaration which will try to duolicate more exactly the 2 dimensional T',lICL reference case with which the 3 dimensional MEKIN case will be compared.
A. Aronson reported that earlier problems in operability of the DWARF code have been solved. We have been modifying :WARF to enable use of an axially detailed model for EOL load follow analyses. This unfortunately makes DWARF run much slower than before.
In retrospect, it seems it would have been wiser to modify NODE to do these calculations: a proposed activity for FY 81 is to program all the necessary searches into SIMULATE, which will replace N0DE. The searches are on boron concentration, axial offset, control rod position, etc.
The BWR rod drop calculations mentioned above are not finished because they are awaiting completion of programming of revised reactivity edits in MEKIN. Also programming changes which allow variable specific heat and thermal conductivity in the fuel have not been tested. These efforts should be completed shortly.
Contact:
M. Dunenfeld, x27577 2220 057 7910240 W
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M. Todosow reported the results of the first load followir.9 eases performed with the modified version of DWARF. These cases duplicated three BOL cases that had been done by A. Busiik a few years ago. The results are essentially identical. This constitutes part of the check-out of the modifications to DWARF. The other part consists of comparing NODE and DWARF unrodded power distributions with and without temperature feedback. A 4th order polynomial fit of the cross sections with temperature for DWARF has provided excellent agreement in the te power shapes.
Therefore, it is considered that the modified code is checked out.
Running of the load follow cases for the EOL constant axial offset control and power distribution control analyses is now in progress.
It is probable that this project will not be completed this fisal year, as scheduled, and will run over at least two months in FY 80.
L. Eisenhart reported on the details of how he is setting up a system for generating cross sections for use in full core 3 dimensional kinetics calculations. He, and fi. Todocaw, also reported on the visits of Radkowsky and Rothenstein to BNL this sumer, and their discussions of the Radkowsky work on the effect of fission products on the Doppler Coefficient.
These discussions again point to the need for additional work to show if there is any reduction of the Doppler in the presence of fission products.
D. Cokinos reported on the status of generation of cross sections for the Ouad Cities reactor. The simulation aives better acreement with data 'for center fuel locations than the core edge. Thi5 is usually the case for most power distribution calculations in the absence of more sophisticated treatment of the core boundar.ies.
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M. Dunenfeld Reactor Physics Section Core Performance Branch Division of Systems Safety cc: See attached distribution 2220 058
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UNITED STATES
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/L h,ygo 3p Mr. Jon Berland 24 E. Victoria Santa Barbara, CA 93101
Dear Mr. Berland:
Your recent letter to Chairman Hendrie concerning the accident at Three Mile Island Nuclear Station Unit 2 expressing your views on nuclear power was referred to this agency for response. We appreciate your concerns and assure you that every effort is being made to ensure the continued protection of the health and safety of the public not only at the Three Mile Island Nuclear Station, but also at all nuclear power plants.
We have taken or are taking a number of actions with respect to all nuclear power plants as a result of the Three Mile Island accident.
Specifically, full-time inspectors have been assigned to each operating plant utilizing Babcock & Wilcox pressurized water reactors like those at Three Mile Island.
In addition, the licensees of all these plants which were not already shut down have voluntarily shut down their plants.
We are issuing confirmatory orders to the licensees of all Babcock & Wilcox reactors like those at Three Mile Island to assure that necessary plant modifications, additional training and revised operating procedures will be effected prior to resuming operation.
Licensees of all operating plants utilizing pressurized water reactors have been instructed to take specific actions with regard to the status of certain equipment, plant procedures, operator actions and facility designs.
Licensees of all operating plants, including those utilizing boiling water reactors, have been instructed to provide us with additional information with regard to their facilities in light of the Three Mile Island accident.
In addition, substantial effort is being expended within this agency to evaluate the factors which contributed to the Three Mile Island accident and to prevent a similar occurrence in the future.
We will carefully review all the information obtained and developed as a result of the Three Mile Island accident and take whatever further action is deemed appropriate.
With respect to alternative methods of energy production such as solar, wind and geothermal, the Department of Energy is the Federal Agency responsible for their research and development.
Our consideration of alternative methods of energy production is limited to the assessment of the environmental impact of each nuclear power plant as part of our overall review of each utility's application for a construction permit or an operating license.
To date, we have determined that alternative methods of energy production such as solar, wind and geothermal are neither technically nor economically feasible to provide the required amount of power at the time it is needed.
2220 059 7910 2 4 0 NL
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AUG 171979 With respect to waste disposal, the Nuclear Regulatory Commission was given regulatory authority over the storage and disposal of all commercially generated radioactive wastes upon its creation in 1974 by the Energy Reorganization Act.
To implement this authority and to provide guidance to the Department of Energy, the industry and the public, we are developing new or revised regulatory standards and guidelines for such storage ard disposal.
These standards and guidelines will require conformance with a fixed set of minimum acceptable performance standards (technical, social and environmental) for waste management activities while providing for flexibility in technological approach.
These standards and guidelines will be designed to assure public health and safety and protection of the environment.
In addition, the Department of Energy has been pursuing a program designed to accommodate the anticipated need for disposal of high-level waste or spent fuel that is expected to accumulate as the nuclear power industry continues to grow.
This program includes, among other things, plans to develop several operations for disposal of high-level wastes in stable geological formations.
The purpose of these facilities would be to demonstrate the acceptability of a specific geological formation for permanent disposal of high-level and transuranic wastes.
These facilities would be treated as permanent disposal repositories.
The Department of Energy is now awaiting a Presidential direction of policy and plans which will occur following completion of studies recommended by an interagency task force formed by the President. There are several methods of high-level waste disposal which are technologically feasible.
The Department of Energy is expected to continue to investigate options to determine whether superior disposal alternatives can be developed.
Sincerely, h
Harold R.,Denton, Director Office of. Nuclear Reactor Regulation 2220 040
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UNITED STATES NUCLEAR HEGULATORY COMMISSION POSTAGE AND FEES PAID WASHINGTON, D. C.
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