ML20079J733
| ML20079J733 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 01/03/1984 |
| From: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8401240403 | |
| Download: ML20079J733 (7) | |
Text
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BALTIM ORE GAS AND ELECTRIC CHARLES CENTER P.O. BOX 1475. BALTIMORE, MARYLAND 21203 January 3,1984 ARTHUR E LUNDVAR. JR.
%CE PRESIDEf47 SUPPLY Mr. Thomas E. Murley Regional Administrator, Region I Office of Inspection and Enforcement U. S. Nucler.- Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Mr. Murley:
Subject:
Calvert Cliffs Nuclear Power Plant Units Nos.1 & 2, Docket Nos. 50-317 & 50-318 Report of Changes. Tests and Experiments
Reference:
(a) 10 CFR Part 50, Paragraph 50.59(b)
As required by Reference (a), attached is a report containing a brief description of the changes, tests and experiments completed on Calvert Cliffs Units I and/or 2 under the provisions of 10 CFR 50.59(a), including a summary of the safety evaluation of each.
items in the attached report are referred to by " Facility Change Requests (FCR)" number.
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Attachment cc: Director of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555
- 3. A. Biddison, Esquire G. F. Trowbridge, Esquire Mr. D. H. Jaffe - NRC 8401240403 840103 f
h l PDR ADOCK 05000317 R
PDR Y
L FCR 75-1163 The recirculntion capacity from Unit i Stehm Generator Main (Unit 1)
- Feed Pumns back to the condenser was doubled from 2000 gpm
- a to 4000 gpm by adding a %.cond line with a control valve and flow orifice, in order to protect the pumps. This modification I
was within the bounds of the Loss of Feedwater Accident described in FSAR Section 14.10. There is no effect on the b
Tecnnical Specifications.
FCR 76-0063 Ventilation louvers were added to control panels 1/2C33, (Unit 1, Unit 2) 1/2C34,1/2C43, and 1/2C63 to eliminate problems caused by F
r E
s, cabinet temperature exceeding instrument. specifications.
t There was no effect on seismic qualification of the panels or on the Technicel Specifications.
a E
FCR 75-0105 Local sample Imes for safety injection and containment spray (Unit 1, Unit 2) systems sample points 1/2-SI-550, 443, 462, & 4167 were r
c e?; tended to improve accessibility and reduce spilling of 3
samples. There was no effect on the Technical Specifications.
5 FCR 75-0268 Low-range pressurizer pressure signals from 1/2-PT-103 were (Unit 1, Unit 2) sent to additional pens on pressure recorders 1/2-PR-100, so that rapid pressure transients in this range may be monitored, as required by NRC I&E Bulletin #75-08.
Recorder loop y
loading remained satisfactory, and there was no effect on the
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Technical Specifications.
' FCR 75-1039 Operation of 1/2-CV-3832 (Component Cooling Water to 7
L (Unit I, Unit 2)
Reactor Coolant Pumps) was changed to air to open/ fall
?-
closed.
This is the conservative failure mode to enhance p
containment isolation. There was no effect on the Technical Specifications.
FCR 75-1103
' Redundant temperature sensors 1/2-TE-5228A, 5232A, 5236A,
(
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, Unit 1, Unit 2) 5244A, & 5248A were moved from the condenser discharge to the discharge conduit in order to provide a more representative P
temperature reading.
The remaining temperature elements g
fulfill the Technical Specliication commitments.
/ (FCR 75-1130 This FCR modified the documentation associated with the Unh 1, Unit 2) installation of nuclear relief valves. Re changes were done to L
/
reflect as-built conditions and to make editorial changes.
Valve tags were also updated. No actual design changes were made so the operation of the relief valves was not affected.
m FCR 76-0128 his FCR allowed the use of a new line of Butterfly valves in (Unit 1) the Service Water System. The manufacturer, Henry Pratt s
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e discontinued the original model. The safety analysb mcluded that the replacement model was equivalent to t' Minal model and thus no unreviewed safety question existeo.
sf FCR 76-0129 The jackscrew from LPSI (Iow pressure safety injection) flow (Unit 1) control, valve 1-CV-306 was removed. The Technical Specifi-cation was submitted and approved as Amendment 20 to our F
operating license.
He Technical Specification was
e standardized to require power to be removed from the valve, with no reference to the Jackscrew, thus deleting the requirement for locking the valve open.
Removal of the Jackscrew did not impair valve operation, and the seismic design was not affected by this slight decrease in weight.
FCR 76-1012 The air supply to control valves 1-CV-517,518 and 519 (Unit 1)
(auxiliary spray line and charging lines 2A and 1 A, resp.) was modified to ensure control valve operability after an accident, in order to prevent boron precipitation in the reactor vessel. A new air accumulator isolation valve (1-CV-2085) between seismic and non-seismic air, and CIS (containment isolation signal) override to containment air supply isolation valve 1-MOV-2080 were added. Post-accident injection of boric acid by the charging pumps was not impaired. All valves required for safety which are downstream of the new valve 1-CV-2085 are designed to assume their safe positions on loss of air.
FCR 76-1028 This FCR provided for design, fabrication and installation of (Unit 1) platforms over the Unit I steam generators to be used for equipment laydown.
No unreviewed safety question exists because the platforms were designed to withstand the seismic loads of this location as well as high live loads.
FCR 76-1071 This FCR added supports to the charging pump relief valve (Unit 1, Unit 2) discharge lines. 'the supports (one for each line) were installed to prevent minor cracking in the charging pump relief valve inlet lines, caused by excessive vibration in the lines. "the modification does not constitute an unreviewed safety question as the piping system remained as is and the piping analysis remained valid.
FCR 77-0054 This FCR replaces the miscellaneous receiving tank inlet "Y" (Unit 1, Unit 2) strainer with a duplex strainer. We duplex strainer has a greater capacity than the "Y" atrainer and does not need mechanical cleaning as frequently as the "Y" type.
Le miscellaneous waste system operability was not affected as a result of this change.
FCR 79-0097 Temporary differential pressure gauges 1/2-PP-4414, 4421, (Unit 1, Unit 2)
& 4428 for condensate strainers were mounted permanently.
The associated strainers are only used for condensate clean-up for 30 days following an outage. There was no effect on the Technical Specifications.
FCR 79-0099 CEDS (Control Element Drive System) wiring for U1 and U2 (Unit 1, Unit 2) partial length control rods was disconnected to protect existing rods from any wiring malfunctions. These rods were not used for operations nor required in any safety analysis. A constant signal (jumpered from shutdown group B) for these deleted rods was supplied to the Metrascope to preclude false alarms.
There was no effect on the Technical Specifications.
o FCR 79-1021 An electric driven centrifugal make-up pump was Installed as (Common) an addition to the fire protection system. he pump takes suction from the fire water tank standpipe and discharges into the fire protection system header. This pump was installed as part of a NRC commitment (NRC Position P-20) to provide adequate capacity to m7et the intermittent use of fire water for purposes other than fire protection.
Automatic pump controls ensure adequate make-up to the fire protection system and improve the operation and reliability of the system.
FCR 79-1033 Part 1 Closure of certain U1 and U2 containment isolation (Unit 1, Unit 2) valves was transferred from CIS (containment isolation signal) to SIAS (safety injection actuation signal), in order to provide diversity of CIS-Initiating parameters, in accordance with NRC I&E Bulletin #79-06B,~ Item 3. Closure of the affected valves does not degrade needed safety features nor cooling capability l
upon SIAS. Initiating parameters for SIAS are consistent with design criteria for CIS. he change does not degrade operabil-ity of the containment isolation valves, and is consistent with ensuring containment isolation on high radiation or pressure.
Part 2 Certain U1 and U2 containment isolation valves were modified to allow CIS/SIAS overrides, as described in NUREG-0578. Administrative controls and keylocked override hand-switches ensure containment integrity.
FCR 79-1055 The control circuits for U1 and U2 containment isolation valves (Unit 1, Unit 2) were modified so that resetting ESFAS CIS (containment isolation signal) would not reopen the valves. This was accom-plished by wiring a reset permissive of all valves closed for the control room CIS handswitches and adding interposing lock-in relays to the sample valves.
NUREG-0578, Section 2.1.4 requires deliberate operator action to reopen the valves. The change did not effect RPS, original design criteria for ESFAS and valve operation, or the Technical Specification.
FCR 80-0007 This FCR provided for tube-type hatches (blockouts) to facili-(Unit 1, Unit 2) tate installation of component cooling heat exchanger tube replacement.
%e existing room and corridor configuration does not allow long tubes to be maneuvered into the rooms without significant damage. The blockout has been designed to meet all reinforced wall criteria and therefore does not violate any technical specifications or structural requirements.
FCR 80-0083 Turbine plant sampling system conductivity recorders 12-CR-(Unit 1, Unit 2)
.6442 were replaced with L & N 250 multipoint recorders in order tot 1) add Hi-H1 alarm capability to the existing Hi alarm for all points; 2) add individual alarm commutation
' capability for all points so an alarm will not prevent the operator. from knowing when another alarm occurs; and 3) facilitate switching between H1 and Hi-Hi alarm setpoints as warranted by plant conditions such as startup.
This NSR equipment is not mentioned in the Technical Specifi-cations.
FCR 80-0098 This FCR increased the minimum required volume of solid (Unit 1, Unit 2) granular trisodium phosphate dodecahydrate (TSP) from 75 cubic feet to 100 cubic feet. Since the fuel cycle duration was increased to 18 months, it was necessary to increase the boron concentration to offset the increased core reactivity in accident analysis and for shutdown margin control. With the increased boron concentration, it was necessary that the minimum volume of TSP be increas d to return the pH of the borated water of the ECCS to 7.0. His change was reflected in technical specification 3/4.5.2.e.3, per Amendment No. 31.
FCR 80-1012 The unlined 24" Pratt butterfly valves 1-CV-5206, 2-CV-5206, (Unit 1, Unit 2) 1-CV-5208 and 2-CV-5208 and the 30" Pratt butterfly valves 1-CV-5210, 2-CV-5210,1-CV-5212 and 2-CV-5212 in the salt water system were replaced with Pratt rubber lined butterfly valves to prevent corrosion. The new valves meet the same design specification and quality requirements as the original valves.
The integrity of the valve is improved due to the improved corrosion characteristics.
The valves use the existing air operators and the function of the vahes remains the same. There is no impact to the technical specifications.
FCR 81-0026 CEDS permissives IRG and ISH from the Ul and U2 plant com-(Unit 1, Unit 2) puters to shutdown and regulating CEA programmers were deleted. This allows shutdown CEAs to be inserted within the Technical Specification limits even though the regulating CEAs are not completely inserted, and regulating CEA's to be raised even though the shutdown CEA's are not completely withdrawn. He CEAs may thus be reoositioned to reduce CEA guide tube thinning. He shutdown CEAs are limited to a range of 129" to 136" by Technical Specifications. Technical Specifi-cations and administrative controls help to ensure that safe shutdown margins are maintained and that power distribution limits are consistent with RPS setpoints. CEA ejection acci-dent analysis assumptions were maintained and thus no unreviewed safety question existed.
FCR 81-0040 This FCR covered the Installation of additional eight hour bat-(Unit 1, Unit 2) tery-operated emergency lights at the manual operators for the main steam bypass valves to the auxiliary feedwater pumps. This change was necessitated by NRC auxiliary feed-water recommendation which required adequate emergency lighting in these areas. This modification was installed as an aid to operating safety related equipment and did not affect the functional operation of the equipment.
There was no impact on the technical specifications.
FCR 81-0047 This FCR provides for additional metal Q-Deck ceiling in the (Unit 1, Unit 2) ceiling of the hallway adjacent to SFP area. Similar ceiling was installed in the same hallway under Security Plan FCR 77-
- 59. This new portion provides the same level of security. He
Installation is NSP, except for the installation of wall anchors which conformed to civil installation standard.
CS-5 for seismic installation.
FCR 81-0065
'Ihis FCR covered the installation of additional electrical (Common) power feeders to machinery which was either relocated or purchased new for the machine shop on the South end of the North Service Building. This work was consistent with the electrical design criteria contained in Section E of the FSAR and did not effect the operation of the plant nor have any affect on the Technical Specifications.
FCR 81-1004 This FCR covered the installation of new remote control (Common) consoles in the Main Control Room and Classroom #1 to be used for radio communications in connection with the Emergency Response Plan. This work was consistent with the electrical design criteria contained in Section E of the FSAR and will not affect plant operations nor have any affect on the Technical Specifications.
FCR 82-0101 This FCR added a spacer between the drive nut and top of the (Unit 1)
ICI nozzle flange #6 in position L-4.
The instrument was received from the manufacturer with insufficient thread length. The spacer was fabricated from materials equal in properties to the drive nut and served to insure full engage-ment.of the detector shaft with the drive nut. The operation of the ICI assembly is in no way affected by this installation.
t bcc Messrs.
A. E. Lundvall C. H. Polndexter C. H. Cruse R. H. Kent
- 3. A. Tiernan R. F. Ash / File L. B. Russell R. M. Douglass R. C. L.' Olson A. R. Thornton D. W. Latham
,