ML20028C873

Forwards Rept of All Changes,Tests & Experiments Performed Under 10CFR50.59(a) During 810615-820630.Safety Evaluation Summaries Included

ML20028C873
Person / Time
Site:	Calvert Cliffs
Issue date:	01/03/1983
From:	Lundvall A BALTIMORE GAS & ELECTRIC CO.
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8301140253
Download: ML20028C873 (7)

Text

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BALTIMORE GAS AND ELECTRIC CHARLES CENTER P.O. BOX 1475 BALTIMORE, MARYLAND 21203 AnfHun E. LUNOVALL. JR.

vice raceoem

sum, Mr. Ronald C. Haynes Regional Administrator, Region 1 Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 I

Subject:

Calvert Clifis Nuclear Power Plant Units Nos.1 & 2, Docket Nos. 50-317 & 50-318 Report of Changes, Tests and Experiments

References:

(a) 10 CFR Part 50, Paragraph 50.59(b) l (b) BG&E letter to NRC dated June 15, 2981 from A. E.

Lundvall, Jr.

As required by Reference (a), attached is a report containing a brief description of all changes, tests and experiments completed on Calvert Cliffs Units 1 and/or 2 under the provisions of 10 CFR 50.59(a), including a summary of the safety evaluation of each. This report covers the period from our last such report, Reference (b), through June 30,1982.

Items in the attached report are referred to by " Facility Change Request (FCR)" number.

Very truly yours,

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AEL/ERZ/gvg Attachment cc:

Director of Inspecticn and Enforcement U.S. Nuclear Reguletory Commission Washington, D.C. 20555

3. A. Biddison, Esquire G. F. Trowbridge, Esquire Mr. D. H. 3affe - NR G g301%

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FCR 74-0013

. This FCR modified thE valve stem on 1-51-447 whidh was sheared

'(Unit 1) during routine operations.;The remaining portion of the_ stem was modified to accomedate the handwheel. The pressure boundary.

Integrity, operability and operating characteristics of the valve were unaffected.

There. was _ no 7 impact on 7 thef technical

. specifications.-

FCR 75-1003 This FCR added narrow range pressure and levelindication to the (Unit 1, Unit 2) safety injection tanks and narrow range pressure indication for the refueling water ~

modification improvad the.

tanks.

The monitoring capability for the tanks and had no effect on the technical specifications.

FCR 77-0004 The existing - 3/4" diameter lifting eye bolts in the steam (Unit 1, Unit 2) generator primary side manway cover were replaced with -1" diameter bolts as part of a modification to retap the threads in the bolt holes, which were damaged.. This modification did not '

decsease the reactor coolant presure boundary integrity of the manway cover and did not affect the technical specifications.

FCR 77-0030 The replacement Transmation isolators for the field transmitter (Unit 1, Unit 2) signal isolation from the sensor bistable units of both the Reactor Protective and Engineer Safety Features Actuation System were -

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modified to match the time response characteristics of the original " Isolators." Neither the approved design criteria nor the technical specifications was affected.

NCR 77-0055 The previously removable main. steam isolation' valve (MSIV)

(Unit 1, Unit 2>

monorail system was upgraded to a permanent installation.

Originally, the system was installed only during periods of maintenance on the MSIV's and actuators. As a result of a design review and seismic analysis, it was determined that the MSIV.

monrail system could be permanently mounted with no degradation of plant safety.

There was no impact on the technical specifications.

4 FCR 77-0124 This change was made for the purpose of installing and evaluating (Unit 1, Unit 2) a cartridge assembly for the plunger and packing on a charging pump. The modification was limited to one chamber of one pump so that if the packing were to fail on the pump being evaluated, the redundant pump would still be operable. The modification did 4

not alter the function of the pump or packing being evaluated and

- t had no effect on the technical specifications.

FCR 77-0143 This modification rerouted the discharge piping for the (Unit 1, Unit 2) concentrated boric acid tank discharge relief valves, RV-132 and.

RV-141, so as to discharge into the top of the boric acid storage tanks, thus facilitating the removal of the valves for periodic testing.

As originally installed, the boric acid storage tanks would have to be drained each time the valves were to be tested. The modification did not alter the design function of the valves. There was no impact on the techncial specifications. f

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y s.t FCR 77-0171 This change involved the manufacture of spare sflait sleeves for (Unit i, Unit 2) the salt 1 water! pumps. The spare shaft sleevesiwere~ initially fabricated from thelsame material specified 'for the original design._ ~ The Lsleeves were 'then coated with.monel to improve wear resistance. =The. modified shaf t sleeves,will increase ~ the -

reliability of the salt water pumps, with no adverse. effects. The technical specifications were not affected.'

FCR 78-0008 -

This change revised the applicable. specification to' allow the use

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(Unit 1, Unit 2) of hermetically _ sealed root stop valves for the steam generator level transmitters. _ The original valves were suoject to periodic -

. packing leaks, and' the use of the hermetically sealed valves should alleviate this problem. The modification will not decrease-the functionability of the valves and will not affect. steam i

generator level indication or. the technical specifications..

FCR 78-0010 A spool piece was installed in the blowdown line of steam (Unit 1) generator #11 under this modification in order to conduct a study on'the reduction of corrosion and contamination in light water reactors. The spool piece and affected piping are non-safety related. - The pipe-hangers used are safety-related and are designed in accordance with code requirements. The modification has no effect on the operability of the SG blowdown system or the technical specifications.

FCR 78-0051 This modification installed a flushing connection to the inlet of (Common) the liquid waste discharge monitor to allow flushing the monitor to remove any residual radioactive material.

The flushing connection was designed and -installed in accordance with the original design specifications. The modific_ation should improve the validity of the monitoring system by removing spurious contributions to background activity. There was no effect on the technical specifications.

FCR 78-0061 This change involved the brazing of the disc bushing and disc to (Unit 2) prevent loosening of the the saltwater pump discharge check valve drive plate. The modification should prevent loosening of the drive plate, resulting in enhanced operability of the check valves during normal operation.

FCR 78-0117 This change defeated only the CVCS flow signal in the control (Unit 1, Unit 2) scheme for the Reactor Coolant Waste degassifier vacuum

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pumps. Mechanical problems with the lever controls caused by excessively high vacuum in the degassifier were eliminated.

Since a low vacuum signal still existed and would start the degassifier pump, pump operability and plant safety ' were unaffected. There was no effect on the technical specifications.

FCR 78-0126 A 3/4" Isolation valve was installed upstream of the pressurizer l

(Unit 1, Unit 2) liquid sample control valve, which is located in a high radiation area. _ By installing a redundant valve in a low radiation area, l

personnel exposure was reduced.

The new installation was analy:J to ensure conformance with the. original design criteria. Sample system operability: was not affected and no techncial specifications were involved.

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FCR 78-0129 This : modification involved : machining "and refinishing of

-(Unit 1, Unit 2) deteriorated areas of th'e. saltwater pump shafts.: The machined area. was; rebulIt !with stainless: steel spray to obtain; required design dimensions.i This_ procedure allowed reusing the existing shaf ts while retarding repeat wear in the deteriorated areas. -The shafts as modified were determined to satisfy the original design criteria, and saltwater pump operability was not compromised.

There was no effect on the technical specifications.

FCR 78-0134 The ' pressurizer spray valve seals' were converted-from' packing

- (Unit 1, Unit 2) seals c to bellows seals to prevent valve stem and packing degradation. The original design criteria for the spray valves was modified to allow use of this valve design. Valve operability and integrity was enhanced by this ' modification, and there was no effect on the techncial specifications.

FCR 78-1010 This change provided for the _ repair and upgrading cf safety

'(Unit 1, Unit 2) re'ated main steam line supports. The supports were returned to th tir-Original. design basis configuration with modifications to pr sclude future failures.

FCR 78-1024 TIis changed involved an updating of the plant drawing for the (Unit 1) cir.ulating saltwater cooling system. ~ The system drawing was moo 3ied to include a diaphragm valve in each seal water supply _

line to the circulating water pumps as indicated on the small pipe field sketches (FSK). The addition of these valves had no effect on the plant safety portion of the system or the technical specifications.

FCR 79-0014 Sections of the internal area beneath the salt water pum)

(Unit 1, Unit 2) discharge check valves were eroded. A spray metal compourd was applied to these areas to return the wall to minimum thickness and to prevent further erosion.

FCR 79-0037 The existing Auxiliary Feedwater Pump throttle trip valve pin (Unit 1, Unit 2)

(carbon steel) was replaced with a stainless steel pin. Tnis was done to comply with the manufacturer's recommendations to prevent a possible galling problem.

FCR 79-0041 Repairs were conducted on the eroded lining of various sections (Unit 1, Unit 2) of the cement-lined saltwater piping. The repair material will decrease subsequent system erosion, does not affect the structural integrity of the piping, and does not reduce flow through the piping below design requirements. The techncial specifications are not affected.

FCR 79-0051 This-modification improved the latching mechanism for. the (Unit 1, Unit 2) auxiliary feedwater pump turbine trip / throttle valve. Excessive clearances prevented _ secure latching of the valve and in some instances caused a premature valve trip.

This modification increases the reliability of the valve and, hence, the steam supply to the Auxiliary Feedwater Pump Turbines. Therefore, overall plant safety is enhanced. There was no effect on the technical specifications.

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- FCR 79-0128 An audible. alarm was added to the refueling water tank motor (Unit 1, Unit 2) operated outlet valve remote handswitches in order to detect an.

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' inadvertent closure of the valve. sThis modification enhances the operational availability of the refueling water tank; and has no effect on the techncial specifications.

FCR 79-0133 The linkage bushing-for the turbocharger damper. valve was (Unit 1, Unit 2) reamed out to remove galled -areas.

A new bushing was fabricated with allowance for the increase in diameter.- The excessive wear.had resulted from'a' lack of lubrication. The function of the damper was not changed, and the modification i-was performed to original. specifications.

The technical specifications were not affected.

FCR 79-0135 A filter was installed in the bypass line of the filtration / drying (Unit 1, Unit 2) system of each switchgear room air conditioning unit. Previously, when the filter-dryer differential pressure decreased and the by-

. pass was employed to allow repairs, foreign matter entered.the compressor internals. The reliability of the air conditioning units is now increased. The new filter is mounted seismically. System operability is enhanced, and the techncial specifications are not affected.

FCR 79-0136 The capacities of the thermal expansion valves on the switchgear (Unit 1, Unit 2) room air conditioning units were increased to match the load requirements of the system when operated continuously. The change in valve capacity was within the design criteria of the air conditioning units.

There was no. effect on the technical specifications.

FCR 79-0145 Vibration eliminators were added -to the receiver pressure (Unit 1, Unit 2) regulating lines on the switchgear HVAC system. These lines had experienced periodic failure due to the vibration commonly 1

encountered during operation.

The change will reduce the possibility of a receiver failure and thus increase system reliability. The technical specifications were not affected.

FCR 79-1010 This change modified the containment emergency air lock so that (Unit 1, Unit 2) the inner door may be tested from -the inside chamber, and the i

outer door tested from outside the containment.

The modification had no effect on the structuralintegrity of the doors j

or the techncial specifications.

l FCR 79-1030 This change modified the reactor protective system to provide a (Unit 1, Unit 2) reactor trip on high differential pressure between steam generators.

This change was necessary to provide additional over-power margin for the 18 month fuel cycle main steam line break analysis. The modification was performed to meet the design criteria for the 18 month fuel cycle, which was reviewed i

and approved by NRC.

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FCR 79-1031 In response to NRC I&E Bulletin 79-04,'which identified certain (Unit 1, Unit 2)

Velan check ? valves: as.having ' weights different !from,those -

published by the manufacturer, the piping systems containing the questionable - check valves.were reanalyzed to confirm the:

. adequacy of the piping.and supports.' TheTresults'of this review showed that the resultant stresses from'the reused valve weights were within allowable ' limits. - There was no impact on the technical specifications.

FCR 79-1048 l The containment air cooler fan motor terminal lugs were replaced

- (Unit 1, Unit 2) with ' a ' offierent style in order to find a more functional termination that would allow motor servicing without continually shortening the leads.

The lugs were recommended by the manufacturer and are. equivalent to the originally supplied parts in ' terms of function and quality. The technical specifications

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were not affected..

FCR 80-0022 _

This change provided position indication for the reactor coolant (Unit 1, Unit 2) letdown relief valves (RV-345/354) and an audible alarm to indicate that the letdown line is relieving to the Reactor Coolant Waste Receiver tank. The alarm warns the operator to take the necessary actions to. prevent an uncontrolled. release of radioactive liquid. The modification did not involve the technical

- specifications.

FCR 80-0085 The remote _ handswitches for the containment sump - drain (Unit 1, Unit 2)

Isolation valves were modified to prevent inadvertent venting of the containment atmosphere to the auxiliary building. This was accomplished by making the handswitch a spring-return-to-close device. The original ESFAS design criteria are unchanged, and the techncial specifications are not affected.

i FCR 80-0110 This change involved the fabrication of a wrist pin for a hydraulic (Unit 1) snubber when a replacement pin was not immediately available.

The wrist pin was manufactured from identical materials and machined to the required dimensions as the original pin.

FCR 80-0113 Electrical system drawing IE-1 was revised to show the correct.

(Common) configuration of the 500KV switchyard. No circuit configuration has been changed from that which was previously approved by 1.

NRC.

FCR 80-0119 The reactor vessel head missile shield support plate was modified (Unit 1) to facilitate anchoring of the shield. The brackets that were.

modified serve only to laterally restrain motion of the shield and all other supports remain unchanged. The modified installation is consistent with the original design criteria.

FCR 81-0001 This change involved the machining of the stem nut for the (Unit 1) containment spray and safety injection pump recirculation control valve (1-MOV-660).

This change was necessitated when the original stem nut was damaged and no replacement was available. Original design dimensions and material were used for this modification.

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l FCR 81-0021 The safety injection tank' check valve numbering on design l

(Unit 2) drawing M462 was corrected to agree with operating drawing OM462. This was an administrative change only and did not affect safety or the technical specifications.-

FCR 81-1012 Changes were made to the instrument index drawings 'and

_ (Unit 1, Unit 2) specifications to correct errors discovered durirzd the NRC audit of Class IE equipment. Service conditions clarifying the actual service of present Class IE equipment and replacement equipment were amended. Thus, the original desir,n criteria were either maintained or upgraded as required, anc there was no decrease in safety or impact on the technical specifications.

FCR 81-1015 The model of the battery room exhaust fan was changed because (Unit 1, Unit 2) the original ~ model fan is no longer manufactured.

The replacement fan meets all applicable design requirements of the original fan. There is no impact on system operability or the technical specifications.

FCR 81-1031 (Unit 1, Unit 2).

Oil separators were installed in the compressor hot gas discharge lines of the switchgear HVAC systems to reduce' oil migration which ' in the past has caused extensive damage to the compressors. As a result of this modification, system reliability was enhanced.

There was no effect on the ~ technical specifications.

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