ML20073Q815
| ML20073Q815 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/24/1991 |
| From: | J. J. Barton GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C321-91-2131, NUDOCS 9106040007 | |
| Download: ML20073Q815 (15) | |
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A GPU Nuclear Corporation U Nuclear t'e== ~
F coed he f Now Jersey 08731-0388 009 971 4000 Wnter's Direc t Del Numlice May 24, 1991 C321-91-2131 U.S. Nuclear Regulatory Commission Attne Document Control Desk Washington, D.C.
20555 Dear Sirs
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 10CFR50.59(b) Reporting Requirements In accordance with the requirements of 10 CFR 50.59, onewaed are summaries of the changes to Oyster Creek systems and procedures, for the period January to December 1990, as described in the Safety Analysis Heport (SAR).
Attachment. 1 of this report addresaes those activities which directly affected systems /componento described in the san. Attachment 2 of this report addresses those activities for which a GPU Nuclear safety evaluation was performed, due to the potential for the activity to adversely af fect nuclear safety or saf e plant operations, but which do not directly impact SAR systems / components.
If you hsve any questions, please contact Mr. M. W. Laggart, Manager Corporate Licensing, at (201) 216-7968.
Very truly yours,
/
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Barton s
Drc or, oyster creek cc Administrator, Region I NRC Resident Inspector Oyster Creek NRC Project Manager
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1, Hodificatione ficuliikAUCD s Installation of Isolation Valven for Fire Diesel Pump Tout Header Drain Lines (i;E 323559-005, Fev. 0)
OfELLI1 ion of HedlikaLLCD The purpose of this modification was to provide isolation capaLility f or the 3/4" dt ain lines f rom t he 10" Fire Dievel Test Header during Fire Diesel Flow Testing.
Thip isolatien capability was accomplished by adding a 3/4" clote Valve on each of thu drain lineu.
The existing 10 inch Fire Protection cost line recirculates pond water back to the pond through a home manif old cont aining rix 2 1/2" hose valves.
The test line is used to demonstrate operability of the diesel driven ftre pumpn and the capability of theco puttpa to deliver at Icast 2000 GPM with a discharge pressure es 150 peig.
1 The Fire Protection Water System test line le non-poirmic.
The system was originally dusigned, fabricated, installed and tested to the requiremento of ANS1 D31.1.
The test line in enly used daring pun p test ing and lu normally leolated from the remainder of the Fire Protection System by two locked cloned valves (V-9-30 and V-9-31).
This modification provides isolation valves for the test header drain lines so that daring purrp testing all iIow in recorded.
EARLL_Fv_al_uat ion Epa ry:
Given the above deoign featurun, and coupled with the fact that operation of the Fire Protection system will not be altered, it is concluded that no safety concern existo.
The margin of nafety has not been reduced, nor han the probability of occurrence of an accident, or probability of a malfunction been increased by this modification.
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liejl11G11oD 5' ire Diesels Proppure Switch /Pecorder Replacement (SE 323559-004, key. 0) pfgrJI11on o f._ Mod i f ic atioD The purpose of thin modification was to replace the obsoleted fire diesel preocure switch / recorders FP-07 and FP-08 located in the fire diesel control panel.
It was becoming more difficult to calibrate the switch / recorder to an acceptable level and since ihis switch / recorder is supporting Tech. Spec. equipment (i.e.,
the fire diesel automatic start) and spare parts are no longer available, the unit (s) hs.J to be replaced.
Even though the original fire diesel panel was purchased to meet UL standards, Oyster Creek's commitment to corrply with UL requirement 0 was not affected to any significant degree.
This le discussed further in Fire Hazardo Analysis F P h'- 3 2 3 5 59 -004.
The vendor who originally manufactured the control panel, King-Knight, is no longer in business to supply replacement parte, dalety Eval.MALisILEngy:
The offeet or consequences of previouc evaluated accident or equipment malfunctionn will not be affected by this modification because this modification, except for removal of the recorder function, doon not change the f unction of the existing pressure switchen/recordern or the operation of the firo diesel control cabinet.
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This modification will not increacu the likelihood of an accident or malfunction beyond those already postulated for the fire diesel system.
The function of the fire diesel, and its control panel remains unchanged by this modification.
This modification does not reduce the margin of safety of any Technical Specification basis or safety system design associated with the Fire Protection System.
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j Modification: Hydrogen Water Chemistry System and Generator Cooling System (St 402840-001, Rev. 5) pgferlotion of Modifica11ca The purpose of this modification is to install a permanent Hydrogen Water Chemistry (HWC) System to mitigate Intergranular Strese Corrosion Cracking (ICSCC) in the Reactor Coolant piping.
- Intergranular stress corrosion cracking (1CSCC) of austenitic stainless steel piping in DWRs has resulted in costly plant outages, one method shown effective in arresting pipe cracking and pipe crack growth is a process known as Hydrogen Water Chemistry (HWC). HWC consists of maintaining good water chemistry and adding hydrogen to the feedwater. Addition of hydrogen decreases the oxidizing power of the reactor water and reduces its aggressiveness toward plant. structural materials.
j Safety Evaluation Summarve This modification will provide a permanent Hydrogon Water Chemistry System to mitigate Intergranular Stress Corrosion Cracking in the reactor piping during all reactor power levels at which the system is operating.
This system will provide a capability in accordance with the EPHI i
2 Report,
f 1987 Hovisions, with tho exceptions as discussed within.the safety evaluation, which will enhance the plant availability without any safety concerns.
In addition, this modification will provide a safe and reliable supply and makeup of hydrogon to cool-the main generator.
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.This modification'does not involve an unreviewed safoty question or environmental impact.
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nadi 11 ration Fire Protection system riow Meter Modification
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Eeecription of Modification The purpose of this modification is to provide local flow measuremont capability to aid in testing of the diesel driven fire l
pucps (P9-202 A/D).
This moQification will aid in conducting fire pump surveillanco testing to l
preservw the CPUN commitment' for testing of these pumps as requirod by (1) the Oyster Creek Plant Technict Specifications and (2) the ASME Boiler and Prebouro Vessel Code, See' on XI.
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Presently flow measuromont is conducted by a hand hold Pit ot tube.
Thin modification installs a permanent flow measuring devico within thu test lino of the Fire Protection Water System.
SAitty IJAIMa.Ll011.Bwngy: 01ven the design features, and coupled with the (act that operation of the test line will be no diffetent f rom past operat ion, tt to concluded t hat no saf ety concern exists.
Tho margin of paloty has not j
been reduced, nor has the probability of occurrence of an accident, or probability of a malfunction been increased by thin modification. This modification replacos the hand held method of flow measurement for the Firo Protuction System test line with a permanent flow measuring device wit h local indication.
The modification does not impact nuclear safety, nor incroaoes the probability of an accident, nor increamo the probability of a malfunction of equipment.
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821Uha.thn Installation Cf1S! Hatch Tank (SE 312100-001, Rev. 0)
Dffttript ion o.1 Mod LUrAtJ20:
This mini-mod document allows the chem-!Juclear Technicians, under the directions of Group Radwaste Shipping Supervisore, to install a batch tank and hook it up to their current plant connections.
The plant hook up is already approved for use by the CllSI fill head. The purpoco of the batch tank is to allow more flexibility for the Clia! Technicians in oupporting the needs of Rad Waste operations.
A necend major purpoco of the i
batch tank is for ALARA.
Dy using the batch tank loss moves of the fill head will be needod, thereby reducing the overall exposuro to the C!lSI Technician.
Eaftly_ EvaluaLLQn_Eumany The implementation of this document will not adversely affect nuclear safety or enfo plant operationo becauno the function of the ayutem has not changed.
The margin of safety as defined in the baulo for any Technical Speelfication has not boon reduced because the system has no nafety function. Also, the limiting conditions of operation f or tho Solid Radioactive Waste System an described in the Technical Specification are not affected by this document.
ligflLUSAtign Installation of Test Plugs and Test Terminalu for leolation Condenser Valveo V-14-33 and V-14-35 (SE 323500-001, Hov. 1) pffeription of Modificallgn:
This modification eliminatos lifting jumper links for bypanning the overload and/or placing the ovorload relay in the circuit while performing surveillance on the motor operated valvos V-14-33 and V-14-35 in the luolation Condeneur System.
This modification will allow the plant electricians and technicians to place or bypass the motor operated valvo thermal ovorload in the main circuit without disturbing the original designed circuit terminations.
Safety EvAlgat ion _Summaty:
Thic modification providos a capability to perform surveillance testing on Isolation Condenser Valves V-14-33 and V-14-35 without lifting jumpor links.
This modification will not alter designed functions of the Isolation Condencer System.
Thic modification will minimite the possibility of human error when performing the related surveillanco.
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1 This modification does not constitute an unreviewed safety question.
There is no environmental impact due to this modification and there are no changes required to the Technical Specification.
Hedificall2D Elimination of Jumper Installation in Exhaust Fan EF-1-5 Control (HCC Cubicle) Circuit (SE 323560-005, Rev. 0)
Regeription of M 11fien11tD The purpose of this modification is to eliminate 2
the use of an electrical jumper in the control circuit of exhaust fan EF-1-6 whenever the breaker for exhaust fan FF-1-5 is racked out and to maintain the original designed redundancy of the circuit.
This jumper allows exhaust fan EF-1-6 to trip when the Standby cae Treatment ayatem is activated.
I Present design of the trip circuit for the exhaust fan EF-1-6 is such that it uses only a 52 breaker contact off the exhaust f*
EF-1-5.
Whenever the breaker for exhaust fan EF-1-5 is racked out, ai ctrical jumper has to be installed in Con *rol Room Panel 11R between Termi AA-40 and AA-b6 (Ref.
Connection Diagt.m Panel 11R OE 719E207) to allow
,aust fan EF-1-6 to trip when the SCTS System is activated and the exhaust fan EF-1-7 is running.
i safety _ Evaluation Summary:1 This modification provides a capability to rack out exhaust fan EF-1-5 breaker from service without affecting performance of exhaust fan EF-1-6 of Rx. Bldg. Ventilation System.
This modification will'not alter _dosigned functions of the Rx. Bldg. Ventilation System. This modification will eliminate installing electrical jumper in tno control circuit i
of exhaust fan EF-1-6 whenever the breaker for EF-1-5 is racied out.
This modification does not constitute an unreviewed safety questic.
There is no environuental impact due to this modification and there are no changes required to the 'Jachnical Specifications.
d2difications Augmented Off Oas Panol EE-OD-1 Pecorder Upgrade (SE 400773-006)
Decerintion of ModificallED:
This modification replaces certain existing A00 recorders, located on panel EE-OD-01, with new recorders that will minimire problems of calibration and maintenance.
The existing recorders are prone to f:llure and the parts necessary to maintain them are hard to obtain or not available at all.
Safety Eve 14Allon. Summary:
The effect-of consequenceu of equipment malfunctions will not be affected by this modification because this 3
modification does not change tho function or failure mode of the existing chart recorders.
j This modification will not increase the likelihcod of an accident or malfunction beyond those already postulated for the Augmented Off cas system.
I The functions of the recorders replaced by this modification wi:1 be unchanged, and the likelihood of an accident or malfunction should be unchanged.
This modification does not reduce the margin of safety of any technical specification basis or safety system design associated with the Augmonted off L
I cas System.
This modification only addressos strip chart recorders which are not required for Tech. Spec. compliance.
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l This modification will not involvo/cteatu any non-nuclear envi ronn.ent al i ripa ct.
These recordere do not have any environmental impact what-no-ever eit hes nuclear or non-nuclear.
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Ref ueling Plat f or m Replacen.ent (SE 408708-001, Rev. 3)
ECLG111*tLQIL9Lh2dlllC411CD :
The overall replacenent refueling platform height, width and rail span are cortparable to the existing t ridge.
The weight of the new bridge, approximately 47,000 poundo, is greater than the existing bridge weight.
In addition, the existing 30-pound rails have alignment and levelnees deficiencies decerit ed in CL Safety Evaluation of Refueling Platform, CE !1uclear Enetgy FCE-Obl089, dated Octcber 1969.
'Ihe exieting rails will be replaced with 00-pound rails with twunting adjuotr:ent u provided to correct the deficiencies.
fAfety EvalH11cn FarAn":
This rnodif itation does not violate any existing license requiremento or regulations.
The enly design change of significance is the additional weight of t he flF500 n ast relative to the current mast.
The proposed replacement ef the refueling platform satisfies the requiremente of lOcFRLO.59. The change in the refueling mact design will not involve a s!gnificant increase in the possibility or consequences of an accident previously evaluated.
The fiFLOO mast is designed to match or exceed all aspects of the mast now in ure.
The probability of f ailurn of the 11F500 and of the e isting mast are both judged to be very small.
In addition, the x
consequences of a puel llandling Accident. using the ^ocurrptions contained in the Oyster Creek FSAR are not changed, and are independent of the mast design in current use.
The change in the refueling mast will not create the possibility of a new or different kind of accident from any accident previoonly evaluated.
The liF500 mast is similar enough in design and function to the existing maat so as not to creat e the possibility of a new or different kind of accident.
Using the new mast does not involve a reduction in a trargin of saf ety.
The setpoint changes allou for the increased weight of the new n, ant, i.e.,
the difference between the now setpoint and the weight of the 11F500 mact is approximately the same as the dii'erence. between t he current cetpoint and the weight of the existing mast.
Altnough the new setpoirit exceeds the weight of the fuel assembly, the interlock will be initiated due to the total weight of fuel, grapple and mast section being greater than the revised cet point.
It is concluded that the proposed refueling platform retrofit will not result in an unroviewed safety question as defined in IOCFR50.59 and that the proposed replacement can be made under the provisionn of 10CFREO.59.
4 liodi f ifallCD s Removal of Hydrogen Generator Cooling Supply Paellity (SE-402909-001, Rev. 0)
Ongtnintion of ModificatinDi The purpose of this modificatic'n was to removo the hydrogen bottle storage facility located in the yard near the south wall of the turbine building. These bottles currently supply hydrogen for generator cooling.
As part of a separate modif ication, hydrogen for generator cooling will be supplied f rom t he bulk hydrogen f acility installed as part of the Hydrogen Water Chemistry System.
The new supply facility will render obsolete the existing hydrogen bottles along with the fare protection deluge system and fire detection system associated with the hydrogen protection deluge system No.
I which also protects the Main Transformer IA, Auxiliary Transformer and Main Generator Dus Penetration.
This modification will remove only the portion si the deluge system associ st ed with the hydrogen bottle otorage racks.
The mtdification also includes removing the f our thermal fire detectors located above the hydrogen bottle storage racks.
Ea.ff.11 fv31uMion hmny The removal of t he hydrogen bottles and associated fire protection / detection systems does not create a possibility for an accident or n 41 function of a dif f erent type than any previously identified in the SAR as we are removing a portion of the fire protection / detection system along with the_harard for which the system was installed.
The margia of safety, as defined in the basis for any Technical Specification, has not been reduced, because the portion of the fire protection deluge system No. 1 being removed and the fire detectore being renoved are not included in any Technical Specification as equipment which must be operable.
The removal of the hydrogen bottles and associated fire protection / detection systems will not violate any plant Technical specification or other licenso requirement or regulation.
The removal of the hydrogen bottles and associated fire protection / detection systems will not have any impact on the level of fire protection afforded to the other components protected by the fire protection deluge system No.
1.
This modification will improve safety by the removal of an unnecessary fire hazard.
i M2dification:
Hetirement of Makeup, Condensate Demineralizer, and Protreatment System (SE 402885-002, Rev. 1) l Reggtlption of Modif1 cal 12D:
The purpose of the modification is to retire the regeneration capabilities of Condensate Domineralizer System and those portions of the Pretreatment and Hakeup Demineralizer Systems not required to support the_new Pretreatment Domineraliter Mobile Trailer System.
The scope of this modification excludes the equipment already added or deleted under GPUN Installation Specifications OCIS-402885-001 and OCIS-402885-002 and is covered in SE-402885-001.
Safety Evaluation summary.:
The addit' ion of packaged water treatment equipment and subsequently retirement of some existing equipment as described in this l
. modification will improve the performance of the existing makeup water systems without creating an unreviewed safety question or increasing the potential environmental impact.
The modification does not involve or interface with any safety related system.
The modification described in SE 402865-001 and this safety evaluation will produce an overall reduction in waste discharged by the ariginal system design.
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Mgdificatient Isolatten condensers Local Level Indication Gaugen (SE 402871-015, Bev. 0)
Orgtrittien of ModillfALIED:
The present isolation condenser level control system does not have a local level indicator which will aid when adding make up (demineralized water) via the grab cumplo line. At one tin.e, a Tygon Tubo was l
installed to provide level indication but has been removed.
This modification will allow the makeup to be added utilizing the local level indicator and thereby eliminating the checking of the level with the Control Room and requiring an operator's tsme.
Since this gauge will be connected and mounted adjacent to the existing cafety related instrument components, this modification will be seicmically supported and in clacsified as " Regulatory Required".
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$jtfety Eva luat ion _ Sgnn_gtry:
Since this modification is connected to the three valve inanif old vent valve, which will remain closed except when adding make-up via the grab sample line, this modification will be ceismically supported and classified as " Regulatory Required".
The purpose of this modification lo to provide local indication of the water level in the isolation condensors and thereby eliminate involving Control Room personnel while adding demineralized water make up via the grab nample line.
This modification le classified as
" Regulatory Required".
This modification does not reduce the margin of safety or= increase the probability of an accident or the possibility of an accident not previously defined.
Engi11 ration:
Water Chemistry Monitoring System (SE 402763-001, Rev. 2)
Dererietion of dqdificatign The purpose of this Water Chemiotry Monitoring System modification is to provide upgraded capability to take 11guld samples for laboratory and/or inline water chemistry analysis an a basic for control of the reactor water chemistry with improved accuracy, reduced radiological exposure to chemistry personnel, and ease of taking the required samples.
This will be accomplished with the addition of a Reactor Water sample Station (RWSS) and an Electro-chemical Corrosion potential Monitoring System (ECPMS) in addition to the existing reactor water sampling sink, the addition of inline monitore to supplement grab samples taken at the existing Feedwater Sample Sink (FWSS) via a final Feedwater f acility and the upgrade of existing nietale samplers at both the Condeneate Sample Sink (CSS) and FWSS.
Ealgly _ Evalu at ion Sunea ry:
This modification will provide a Reactor Water Sample Station designed to permit the continuous monitoring and periodic grab sampling of reactor water and will add monitoring capabilities for the feedwater Condensate System to improve key chemistry parameter monitoring while maintaining radiological exposure to personnel ALARA.
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.This Water Chemistry Monitoring System upgrade will assure representative and useful samples, minimite lab analysis time, imprcve accuracy using inline instrumentation and reduce radiological exposure to chemistry pernonnel.
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In addition, this modification will provide an Electro-chemical corrosion Potential Monitoring system to indicate react or water chemical conditions conducive to IGSCC so that mitigating corrections can be made.
This modification is not required for plant safety and will be designed and
. constructed in a manner which will have no adverse affect on plant cafety.
l Therefore, the modification does not result in an unreviewed safety question or environmental impact.
Modificati.gn Repaired Transformer M1A Installation and Reconnection (SE 992100-002, Rev. 0)
Descriptien, of Mo4Lilratign The purpose of this modification in to reconnect the repaired main transformer M1A to the 23KV isolated phaso bue and various plant auxiliary systems.
This modification will also be utilized to rearrange wiring and cabling within the junction box (TD# 37-4) located at the south-end J
of the 1C Condenser-Bay in order to terminate auxiliary transformer differential CT cable, main transformer neutral CT-cable, main generator CT cable, and 230KV bus differential CT cable in a new junction box located near the M1A transformer to facilitate testing by JCP&L.
Safety Evaluation Summary:
This modification installe the repaired main transformer M1A.
In this mode of operation, the plant on-site electrical distribution system remains poworod from the main generator via the Unit Auxiliary Transformer in the same manner and extent as the original plant design. There is no change to the operation of plant safety systems, Technical Specification requirements and limits or adverse impact on the plant environment.
No experiments or tests are performed, which would adversely affect the plants safety.
Hence, this modification to install the repaired
- main transformer M1A does not affect the margin of cafety or create an unreviewed safety question as described under 10CFR50.$9.
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Modification:
Cable Spread Room Deluge System # 4a Mod.
(SE 000811-008, Rev. 0)
Descriotion of Modification: MNCR 87-132 identified portions of cable trays 15, 16, 19 and 20 in the lower cable spread room which were not adequately covered by direct water spray.
Therefore, to supply the required coverage a modification was done to include full spray coverage on the trays.
Eafety Evaluatjon Summary: This modification adde direct water spray coverage on previously uncovered sections of cable tray 19 and 20 in the cable Spread Room.
This modification will not adversely impact the plant fire protection system and will not_ require changes to licenoing bacia documento.
Also, safety-as defined in licensing basis documents will not be reduced.
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'9" Modificatinn 30" overboard Discharge Sartple Point (5E 3?f5153-002, Rev. 1)
Descrir11on of Modification:
The purpose of tnis modification is to provide a 3" stand pipe with threaded cap end into the existing 30 overboard discharge as a sample port to facilitate grab type sampling activities.
A portable pump l
will be used to withdraw samples.
The reason for this modification is to provide a safe place for personnel to take grab type samples.
Without this modification, grab samples will have to be taken at the outlet of the 30" overboard discharge.
Perconnel must walk
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approximately 150 ft. along a 24" to 30" semi-paved area outside the protected fence to reach the discharge in order to take the sample.
The sample is taken by lowering a bucket tied to a rope into the dincharge.
At this point personnel are kneeling on a piling directly over the canal.
When the walkway is covered with snow and ice, it is possible for personnel to fall into the water. This is considered to be a harard which is likely to cause death or serious physical harm.
Therefore, this modification increases the safety margin for the personnel l
Safety Evaluation Summary:
This modification is Not Important to Safety, there are no seismic-requirements for the system, and there are no quality assurance requirements for this modification.
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............................................................................ II. Temporary Variations Hodifications Temporary Demineraliser system (SE 312100-003, Rev. 0)
Description of Modificatica:
A Temporary Demineralizer System was to be installed at Oyster Creek to process water collected in the Chem Waste / Floor Drain Collection Tanks, WC-7-1A/B/C, in lieu of using the Radwaste concentrators, WC-E-1A/D.
The initial Domineralizer system is expected to be in operation for 2-5 years.
Safety Evaluation Summary:
The plant margin of safety is not reduced by use of this system because the domineralizer system does not affect any system
-associated with technical specificatione defined anargins of safety.
Nuclear safety and safe plant operation are not adversely affected.
There is not an increace in the probability of consequences of an accident previously evaluated
~1n'the SAR.
Important to safety equipment is not adversely aff ected.
The system does not create an accident or malfunction of a type previously identified in the SAR.
Ho Technical Specifications or other license based document is violated.
No radiological safety concern exists.
Use of this system complies with the intent of Reg. cuide 1.143 to "... provide reasonable. assurance that... radioactive waste management... systems are designed, constructed, installed and tested on a level commensurate with the needs to protect the health and safety of the public and plant operating personnel.
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Hodification Installation of a Gag for Valve V-1 Description of ModificatioDI This temporary variation installed a gag on valve V-1-151.
This valve is the inlet valve f or the Conderiaate Deaeration Steam into the "B" Condenser. The system is designed to be used to assist in the deaeration process when the hotwell condensate is below saturation temperature.
The purpose of the gag is to prevent leakage. The system is not used during plant operations.
EAfety EvaluatioD.5MM RIY8 This temporary installation did not affect a safety related system and is not related to any equipment-important to cafoty as evaluated in the SAR.
The installation of this temporary modification did not create the possibility for any accident or malfunction of any kind previously evaluated.
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~11-Eg;1[finLis t Replacement of Exieting Dreaker with UV/Dreaker (TV 90-13 & 90-14)
ORECE1111ED:
Remove the leads rulplying power to the UV device no t hat the entire UV device may be removed f rom thiu breaker. This breaker will be reinstalled in the cubicle E05 of the MCC 1D21.
Sal 1LLin_hteLiRD.J9fEMy t This con }cnent load will add additional lead which will not affect the DC-2 loading during lece of of f site pwer per technical evaluation performed by Technical Punctions.
Additional loading on Do will not affect the performance of DG per technical evaluation lerformed by Technical Functions (EPGI).
Addition of t his loud on DG will not overload the DG, during loss of of f site power and chall not cause any accident or malfunction.
Due to diesel generator #2 additional loading, tFe performance of DC.*' will not be altered and thus margin of safety is not reduced.
W2jillEAIMa t Dilution Punp Spray Header Connection to the High PresoJre Screen Wash System (TV 89-P4)
OfftI1E112D1 Due to excors foaming in the dilution pun p dircharge channel, a
spray header is required to collapee the foam bubbloo prior to their papuage down the discharge canal.
The installation will be temporary in nature and will involvo 2" PVC pipe with cpray nozzles positioned overy two feet which will provide an overlap of the oprty pattern along the entire length of the header.
The supply line conslate of 1" PVC hace, a bachet strainer, loolation and drain valves which will prevent clogging of the norzleo and provide throttling ability.
The 1" hoce will be connected to the high pressure spray wash header drain valve V-3-47 via a dual garden hoco adapter.
The fcam spray header and a majority of the supply hooe is located outside of the protected area and does not have any offeet on plant systems except the high presuure screen wash cystem and the effect on t he sy st em is addt epped eepar ately.
The drain header in alue utilized as a wash down station which uneo a garden hooe.
Because of the dual wire connection, the foam spray header connection will not interf ere with the ability to use t he wash down station.
EAlf sY EVA19.L!LtLon SEmin't The high pressure ocreen wach eyctem is clasoifiod a0 other" and provido no safety functions.
The system in operated manually anJ is normally used during plant operationa.
The nyctem normally requirop QA/QC involvement, but the nat ure of the instal.ation does not itquire QA/QC review because of the temporary connection and operation of the header will bis controlled outside of the prctocted area.
Following monituting and adjustment to the system, a subnersible pump will be added t enable removal of the line from the HPSW cystem.
The system will be placed into operation by opening V-3-43 and will be controlled at the spray hender by throttling a valve installed at the inlet to the spray header.
In the event of a leak in the line during operation of t he header, the lino can be readily icolated via V-3-43.
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Procedure Changes i
Procedures Special Operation for Control Rode 14-47, 34-03, 34-31 and 42-31 l
Deserlotion of chanage The purpose of the above procedure change was
- .o address the operability of four control rods which have withdrawal stroke times that are outside the acer stance criteria of oyster creek Procedure 235.
These i
control rods are 34-03, 14-47, 34-31 and 42-31 j
These control rods have improved withdrawal stroke times when withdrawn with d
the 104 valve isolated.
The following procedure will be evaluated for operation of these rods:
1,. The 104 valves shall-be closed for rod withdrawal out to notch 48.
2.
For reactor startupe, the 104 valves will be closed when startup connences and will remain closed until the rode reach position 48, at which time thi valves shall be opened.
This period of time should not normally exceed 96 i
hours.
3.
During steady-state operation, where withdrawal of these rods is not i
anticipated, the 104 valves shall normally be maintained open.
4.
For weekly CRD-exercices it will not be required to close the 104 valves for these rods.
- 5. - For a shutdown, 'it will not be requirad to c lose the 104 valve prior to rod
- insertion.
Ilowever, for power maneuvering which requires insertion of these rode (and subsequent wit hdrawal is possible), the 104 valve shall be closed prior to insertion.
Safety Evaluation summary:
This operation will not increase the probability of occurrence or consequences of an.iecident or malfunctions of equipment.
The operation of these control rods with the specified procedure will produce
' acceptable withdrawal speeds and will-not renuit in significant damage tu the drive.
Therefore it does not create the pomelbility.for'a new or different
.l type of accident or malfunction that has already been evaluated.
This operation will not reduce the margin of safety as defined in the basis for any technical specification.
The operation of control rode 34-93, 14-47, 34-31 and 42-31 with the specified procedure in effect will result in acceptable stroke times "or withdrawal and will not reduce the margin of safety as defined in any licensing basis document.
This procedure will not result in significant degradation of control rod drives.
Therefore, this operation will not adversely affect nuclear safety or safe plant operations.. It.does not= involve an unreviewed safety question.
Finally, there are no technical specification changes required to implement these procedures.
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- M2d1[ication: Chlorination System Upgrade (SE 402792-001, Rev. 1) i Description of Modif.itatina The modification provides a codium hypochlorite i
storage and feed system to replace the existing Flecher & Porter 11guld chlorine gas system. The p.imary purpose of the chlorination system is to control biofouling on the beat transf er surf aces of equipment cooled by the l
circulating, 69fvice, and tmergency service water systems. The radwaste l
service water chlorinatisn package is not affected by this modification.
The purpose of the medification wass l
o To provide in',reased chlorination capacity, necessitated by new requirements impoced by the N.J. Department of Environmental Protection with regard to allowable chlorination periods.
o To eliminate the potential hasard of a chlorine gas release adversely l
affecting personnel and operations.
o To increase system availability and reliability by reducing downtime caused by mechanical breakdowns,. corrosion-related failures, and lack of I
replacement parts availability, and by providing capability of wintertime operation.
gaiety Evaluation Summary:
The chlorination system and other affected systems that have no safety functions,.are not required for safe shutdown of the reactor, and are not required to mitigate the consequences of postulated accidents. The chlorination system interfaces with the Emergency Servlee Water System (the only affected HSH system) only when the system is not ope rat ir.g.
Therefore, this modification will not increase the probability of occurronce or
.f the coneequence of an-accident or malfunction in relation to the Emergency Service Water System, since the effect of chlorination will remain the same by using sodium hypochlorite instead of chlorine.
The modification does not affect any of the existing interfaces between the chlorination system and the Energency Service Water or Service water Systems.
In the unlikely event of l
total f ailure of one or both hypochlorite storage tanks,- or-associated piping, with a resultant spill of tank contents to the environment,.there would be no adverse impact on the operation of the Emergency Service water pumps at the intake structure, but the maximum volume of chemical relative to the travel distance and other factors is such that t he emergency equipaent could not be flooded or otherwise rendered inoperative due to this postulated releace. The condensate storage tank, adjacent to the hypochlorite storage tanks, is a nonseismic-tank of far greater size and volume.
The flooding impact of hypochlorite storage tank failure would be minor compared to condensate storago-i tank failure.
The proposed modification will not have any adverse effect on the nuclear safety or the environment.
This modification doeu not create an unreviewed safety question as described in 10cFRt0.$9.
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Modification Off-cas Sample Flow Transmitter (SE 408758-002, Fev. 0)
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ggeerietion of Modi ficat l2D1 This modification consists of replacing obsolete CE/MAC transmitter RH-55 with Rosemount transmitter.
It is classified as i
replacement-in-kind in accordance with Corporate Procedure 1000-ADM-7350.01 (EMP-019).
RN-55 la part of the off-Cao Radiation Monitoring system.
Its function is to monitor the flow of of f-gas sample through radiation monitor and to provide input sinnal to recorder RN-35 (panel lor, red pen) for recording and annunciation purposess window 10r-4-C, "off-cas sample Flow Lo".
Safety Evaluation Summary:
This modifiention consists of replacing obsolet e GE/KAC Transmitter RN-55 with Rosemount Transmitter.
This modification shall not affect safety or nealth of the general public or have an environmental impact. This modification does not constitute an unreviewed safety question as determined by 20CFR50.$9.
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i 02dif.irAL1CD s office liullding Elevator UV Trip Device and circuit (SE 320184-008) peceriotion of Modifica.tign:
This modification addresses the safety concern of I
personnel being trapped in t'.e of fice building elevator during a power loss.
This modification consists of an addition of a new relay and the interchange of l
the existing breaker with one which does not contain an undervoltage trip device. This will permit depressurtaing the elevator's hydraulic system, lowering the elevator and opening the doors at the ground floor with minimal power consumption.
' Safety EvaluatioD_$2VH1Y:
This modification enables the elevator to lower to
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the bottom floor and open its doors during an offsite lous of power.
Its only effect is a small addition to the diesel generator load used to energize the necessary relays.
This load has been evaluated as an acceptable additional load. The modification will not violate any rogulations and does not degrade safe operation of the plant.
1 Modificatio0:
Permanent Shielding at Spent Fuel Pool Gate (SE 402912-001, Rev. 0)
Description of ModJfjrailgn:
The purpose of thic modification was to reduce I
the radiation level in the spent f uel pool gate area on elevation 119'3" and on the refueling bridge in the reactor tuilding.
When moving fuel in the spent fuel pool near the gate, a lockable high radiation area is created on the floor in the. vicinity of the gate; high radiation area is also created on the refueling bridge.
-It is anticipated that the problem will become more severe,
-when row A of rack F (closept to the gates), now empty, is filled with spent fuel.
This shielding will reduce the radiation field in the affected area by approximately a factor of 3.2.
4.
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