ML20126C589

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10CFR50.59 Annual Rept for 1992
ML20126C589
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 12/31/1992
From: Simpkin T
COMMONWEALTH EDISON CO.
To: Murley T
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9212230132
Download: ML20126C589 (12)
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, i commonwe,% Edison D:c:mber 17,1992

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%j/ Downers orove, Illinois 60515 Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Documont Control Desk

Subject:

Braldwood Station, Units 1 & 2 10 CFR 50.59 Ar.nual Report NRC DocketNos. 50-456 and E0_451

Dear Dr. Murley:

Pursuant to 10 CFR 50.59(b)(2), Commonwealth Edison is providing the required annual report for Braidwood Station (Facility Operating License Nos. NPF-72 and NPF-77). The annual requirement is based on the Unit 1 fuel load license (NPF-59) issuance date of October 17,1986.

This report covers the period from 12/19/91 to 6/18/92 and consists of the descriptions and the safety avaluation summaries for changes to the facility described in the Safety Analysis Report. Included also as part of this report are changes made to features of the Fire Protection Program not previously approved by the Commission.

No tests or experiments governed by 10CFR50.59 (a)(1)(iii) were performed.

Currently, the UFSAR and Fire Protection Report revisicns are submitted by December 18 of each year. This date is based on the anniversary of the Braldwood Unit 2 03erating License. These reports cover the period from June 19 of the previous year to J une 18 of the year the reports are due. In order to better coordinate the generation of the above reports and the 50.59 annual report, Commonwealth Er.iison has shifted the reporting date for annual 50.59 reports to match the UFSAR and Fire Protection Re aod Revisions. To accomplish this, an interim report covering the period -

of 6/19/91 to ' 2/18/91 was submitted on June 17,1992. Subsequent 50.59 reports shall be submitted annually on the same schedule as the UFSAR and Fire Protection Report revisions. p Please direct any questions regarding this matter to this office.

Respectfully, D-T.W. Simpkin Nuclear Licensing Administrator cc: R. Elliott-Braidwood Project Manager, NRR B. Clayton-Chief, Branch Chief Rill S.G. DuPont-Braidwood Senior Resident inspector r

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- y Braidwood Nuclear Power Station 10 CFR 50.59 Annual Report 1992 NRC Docket Nos. 50-456 AND 50-457 License Nos. NPF-72 AND NPF-77 1 l 

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  ,_i I. FACILITY CHANGES A .'  MIROR PLANT CHANGES
1. P20-2-90-006
2. P20-2-90-036 B. tiODIFICATIONS
1. M20-1-88-065 and M20-2-88-068
2. M20-1-90-014 C. SETPOINT/ SCALING CHANGES
1. SSCR 87-042 II. PROCEDURE CHANGES A. PROCEDURAL UFSAR CHANGES
1. UFSAR DRP 3-031
2. UFSAR DRP 4-005 B. STATION ONSITE REVIEWS
1. OSR 92-003 C. SIAILON PROCEDJ1RE_.REVIS10HS
1. BwRP 1240-9, Revision 3 III. TESTS / EXPERIMENTS None
i. -

s MIHDR ELANT CHANGE P20-2-90-006 DESCRIETIONt This minor plant change replaces the seal injection filter inlet.and outlet-valves. The existing valves are two inch diameter Kerotest valves. The new valves'are two inch diameter KSB bellows sealed valves.- The existing. valves are prone to through leakage and stem leakage. SAEETLEYALUATION

SUMMARY

1

1. The probability of an occurrence or the consequence of.an accident, or' malfunction of equipment important to safety as previously evaluated in the Final Safety Analysis _ Report is not increased because the new valves
                  -will be more reliable than the existing valves.

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2. .The ponsibility.for an accident or malfunction of a different type than any previously evaluated in the Final Safety Analysis Report is not created because the new valves serve identical ' nctions to the existing.

valves. No new accidents or malfunctions are created by their installation.

3. The margin of safety, as defined in.the basis for any Technical-Specification, is not reduced because the new valves will serve all-the same functions as the existing valves. A modification test will confirm l that the valves have satisfactory hydreulic characteristics to maintain the Technical Specification safety margins.  !
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b 1 687(121092) ZD85G j H 

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l-MINOR PLANT CHANGE P20-2-90-036 IlESCRIPlIQi1 This minor plant chsnge reduces the lift setpoint of 2CV8119, Downstream Letc.cwn Pressure Control Relief Valve, from 300 psig to 230 psig by installing a new spring anc washer assembly. This change will provide added protection from overpressurization to lower elevation components in the Chemical and Volume Control System and related systems. SAEITLIYALUATIGLSWRIAREL

1. The probability of an occurrence or the consequence of an accident, or malfunction of equipment important to safety as previously evaluated in the Final Safety Analysis Report is not increased because the valve body is unchanged and only the spring / washer assembly will be changed. The new setpoint will result in lower maximum pressure in the CVCS system and related systems which will decrease the probability of a malf unction of valves or other components important to safety.
2. The possibility for an accident or malfunction of a different type than any previously evaluated in the Final Safety Analysis Report is not created because only the internal spring / washer assembly is being changed with all of the other characteristics remaining the same. The inadvertent lifting of the relief valve is analyzed for in the UFSAR as well as the failure of the relief valve body.
3. The margin of safety, as defined in the basis for any Technical Specification, is not reduced because the lowering of the lift setpoint will prevent overpressurization due to elevation differences in the CVCS system and related systems. This increases the margin of safety for the CVCS system and related systems.

2 687(121092) ZD85G l i 

  --            -   ---.-____m___     _                       _ - _ _ _ _ _ _ _ _ __ _ _ _

MRDIFICATIQRS M20-1-88-065 and M20-2-88-068 DESCRIEIl0N1 These modifications reconnect fire protection deluge valve alarm hotns for the system auxiliary, unit auxiliary, and main power transformers. SMEILEVALUATION

SUMMARY

t

1. The probability of an occurrence or the consequence of an accident, or malfunction of equipment important to safety as previously evaluated in _-

the Final Safety Analysis Report is not increased because the function and operation of the affected fire protection systems, as described in the Fire Protection Report, is not affected by these modifications which only reconnect existing alarm borns. The design of these modifications is consistent with NFPA Code requirements regarding alarm provisions for fire protection sprinkler systems.

2. The possibility for an accident or malfunction of a different type than any previously evaluated in the Final Safety Analysis Report is not created because the installation of these modifications introduces no new failure modes to impact the ability of the affected fire protection systems to perform their intended functions. This design change utilizes existing spare pressure switch contacts and associated wiring to reconnect existing water flow alarm horns.
3. The margin of safety, as defined in the basis for any Technical Specification, is not reduced because the plant fire protection system is not specifically addressed by the Technical Specifications. These modifications only reconnect existing fire alarm horns. Accordingly, the maroin of safety is unaffected.

3 687(121092) ZD85G ________j 

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tiODIFICAIIQti M20-1-90-014 RESCRIPTIOt{1 This modification replaces the existing opposite division power D.C.-operated 

                 " fall as left" solenoid operated valve-in each train of the hydrogen            .

monitoring system with a D.C. operated " fall open" solenoid' operated valve. With this new configuration in place a loss of power in one ESF division will~ not leave a failed close valve.in the opposiri division. SAEETY EVALUAT10tLSUMt4ARX1

1. The probability of an occurrence or the tvlequence of an accident, or malfunction of equipment important to sh '- as previously evaluated in the Final Safety Analysis Report is not increased because this equipment has no function in an accident other than containment isolation. This function has not changed. The containment isolation function will still occur in the event of a safety injection actuation. The consequences of .,

the accident will not be increased because containment integrity is maintained by the other isolation valves in series. This equipment perfor.ns a containment ibolation function and does not. affect other plaut systems. The probability of a malfunction of equipment-important to anfety is not increased because all other equipment is. unchanged and ' the valve still performs its original isolation function. .The consequences of a malfunction of equipment important to safety does not increase because the equipment functions and systems remain the same. The valves being modified which still perform the containment isolation function.

2. The possibility for an accident or malfunction of a different type.than any previously evaluated in the Final Safety Analysis Report is not created because the UFSAR assumptions for accident: assumes that all containment isolation valves close and remain closed throughout and after the accident valves manually reopened. .The modified valves.will
                          " fall open" upon a loss of a D.C. ESF bus which is different than previously assumed. The containment isolation _will still be maintained through the other valves in series. This. configuration has been submitted to the NRC, evaluated by NRC and found acceptable. :On April 19, 1991 the NRC issued the supplemental Safety Evaluation which
;-                        accepts this modification.
3. Tne margin of-safety, as defined in the basis for any Technical Specification, is not reduced because . valves still: provide containment; isolation function. In the event of a loss of one division of DC ESF-power containment isolation is' maintained and hydrogen monitoring is still achievable.

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R; - SEIPRIliT4 SCALING CHANGE SSCR'87-042 DESCRIPTION 1 This setpoint/ scal'ing change involves increasing the alarm setpoint'for the Hydrogen System Supply Manifold Pressure instrument OPS-1065A/B from 110 psig to 130 psig to eliminate nuisance alarms. EAFETY EVALUATION

SUMMARY

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1. The probability of an occurrence or the onsequence of an. accident, or malfunction of equipment important to safety as previously evaluated in the Final Safety Analysis Report is not increased because'the operating pressure remains the'same. The setpoint/ scaling change is only.to: clear nuisance alarms. Therefore, the probability of an occurrence or the consequence of an accident, or malfunction of equipment important to safety as previously evaluated in FSAR Section 11.3 is not increased.=
2. The possibility for an accident or malfunction of a different type than any previously evaluated in.the Final-Safety Analysis Report is not-created because there is no change-in the design of the system, so the possibility of an accident of a different type has not been created as per FSAR Section 11.3.
3. .The margin of safety, as cefined in the basis for any Technical Specification,-is not reduced because the setpoint change does not affect the requirements or the bases for.the Technical Specifications, particularly 3/4.11.2.4 and 3/4.11.5. (It is to be noted that1 Specification 3/4.11.2.4 has subsequently been deleted, and the-requirements relocated to the ODCM per NRC Generic Letter 89-01.)

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/. UFSAR PROCEDURAId9ANGE UFSAB DRP 3-031 DESCRIP_ TION 1 This UFSAR change invalves making the spent fuel pool boron concentration limit of 2000 ppm a recommended value and setting-1500 ppm as the new minimum value. This is for consistency with an engineering evaluation for the high density spent fuel racks. This study showed that 300 ppm is the minimum value required. Setting 1500 ppm as the limit provides additional margin. SARD[_ EVALUATION SUMMARX1 c

1. The probability of an occurrence or the consequence of an accident, or-malfunction of equipment important to safety as previously evaluated in the Final Safety Analysis Report is not increased because the limit of-1500 ppm exceeds the analyzed limit of 300 ppm.
2. The possibility for an accident or malfunction of a different type than any previously evaluated in the Final Safety Analysis Report is not created because the limit of 1500 ppm-exceeds the analyzed limit of 300 Ppm.
3. The margin of safety, as defined in the' basis for any Technical Specification, is not reduced because the change has no impact to the requirements or bases of the Technical Specifications. 1
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lifjAR PROCEDURAL CHANGE UFSAR DRP 4-005 DESCRIPTIONL-This UFSAR change involves el'minatira i the out-of-service requirement which-removes power f rom valve '<s003. Thit is for consistency with NUREG-0737=and-NUREG-0800 and with similar valves VQ004A/B and VQ005A/B/C.- The VQOO3 valve is a containment isolation valve which isolates the flowpath to the containment Post-LOCA Purge Unit. SAFETY EVALUATION SU}2iARI.t

1. The probabilicy of an occurrence or the consequence of an accident, or malfunction of equipment important to safety as previously evaluated in the Final Safety Analysis Report is not increased because the-change does not affect the safety features of the valve, and the valve will continue to close on a containment isolation signal,.and fail closed on a loss of air / power.
2. The possibility for an accident or malfuaction of.a different type than any previously evaluated in the Final Safety Ana)ysis Report is not created because the valve will continue to, operate as' designed.
3. The margin of safety, as defined in the basis for any Technical Specification, is not reduced because the chango has no impact to the requirements or bases of the Technical Specifications 7

687(121092) ZD85G

se STAT 10tL0tiSITE_REYlEW OSR 92-003 DESCRIETIOHL This onnite review involves changing the lineup of the nitrogen cylinders to normally isolated rather than normally open. This is to provide a backup-supply for the low pressure portion of the nitrogen system. SAEETY_EVEUAT10lLEU191ARYt

3. The probability of an occurrence or the consequence of an accident, or malfunction of equipment important to safety as previously evaluated in the Final Safety Analysis Repott is not increased bscause the nitrogen system is not used to mitigate the consequences of any accident.
2. The possibility for an accident or malfunction of a different type than any previously evaluated in the Final Safety Analysis Report is not created because the change will enhance (increase) the amount of nitrogen avalleble if the low pressure supply were to run low. The nitrogen system does not affect the initial (assumed) conditions for any analyzed accident, nor could the change result in a malfunction of systems or components served by nitrogen so as to create another accident.
3. The margin of safety, as defined in the basis for any Technical Specification, is not reduced because the change has no impact on the requirements or bases of the Technical Specifications.

8 687(121092) ZD850

V SIATION PROCEDURE REVISIQB BwRP 1240-9, Revision 3 DESCRIPTIOt{1 This station procedure revision involves changing the calibration frequency of certain health physics instrumentation-from quarterly to semiannually. This is for consistency with ANSI N323-1978. SAfITLIYALUAIIDtLSUMMAR11

1. The probability of an occurrence or the consequence of an accident, or malfunction of equipment important to safety as previously evaluated in the Final Safety Analysis Report is not increased because the change has no impact to the accidents discussed in the FSAR.
2. The possibility for an accident or malfunction of a dif ferent type. than any previously evaluated in the Final Safety Analysis Report is not created because the health physics equipment, shculd they fall or malfunction, would not affect plant operations.
3. The margin of safety, as defined in the basis for any Technical Specification, is not reduced because the change has no impact on the requirements or bases of the Technical Specifications.

i 9 687(121092) ZDB5G 

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