ML20205R857

Final Deficiency Rept Re Emergency Feedwater Sys Design Flow Requirements.Initially Reported on 860425.Emergency Feedwater Pump Constant Flow Recirculation Line Replaced W/ New Safety Class 3 Recirculation Line for Each Pump

ML20205R857
Person / Time
Site:	Seabrook
Issue date:	05/10/1986
From:	Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
SBN-1045, NUDOCS 8606050505
Download: ML20205R857 (4)

Text

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~# SEABROOK STATION

' Engineering Office ,

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~ _J g May 10, 1986 SBN- 1045 T.F. Q2.2.2 United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 Attention: Mr. Richard W. Starostecki, Directo r Division of Project and Resident Programs

Reference:

(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) Telecon of April 25, 1986, D. Maidrand (YAEC)/P. Hannes (YAEC) to J. Grant (Region I Inspector)

Subj ect : Final 10CFR50.55(e): Emergency Feedwater System Design Basis Flow Requirements

Dear Sir:

On April 25, 1986, we reported a potential 10CFR50.55(e) deficiency, Reference (b), regarding the Emergency Feedwater (EFW) System operation.

We have completed our evaluation and have determined the existence of a reportable deficiency.

During the Seabrook EmerFency Feedwater System Hot Functional Testing, system deficiencies were experienced. These items have since been corrected to ensure complete system reliability. The deficiency being addressed in this report is relative to achieving system flow re-quirements with continuous EFW pump recirculation.

Seabrook EFW System design basis requires the system to deliver a total minimum flow of:

a. 470 gpm to at least two (2) intact steam generators for a Condition IV feedwater line break scenario.

b. 650 gpm to four (4) steam generators during a Condition II loss of normal feedwater flow event with one (1) pump opera-tional (with and without of fsite power available). The total 650 gpm is based on the additional heat input generated by the operating reactor coolant pumps during the most conser-vative loss of feedwater event.

9 8606050505 860510 PDR ADOCK 05000443 /.

S PDR Seabrook Station Construction Field Office . P.O. Box 700 . Seabrook, NH O3874

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United States Nuclear Regulatory Commission Attention: Mr. Richard W. Starostecki Page 2 f

s The above flow requirements are achievable with the current EFW System design as modified subsequent to Hot Functional Testing.

I DESCRIPTION OF DEFICIENCY Evaluation of the Seabrook Emergency Feedwater System following Hot

Functional Testing revealed the inability of the subject system to provide the. required 650 gpm flow necessary for a loss of normal feed-water event. This deficiency is attributable to the EFW pump (s)

recirculation line configuration. This recirculation scheme posed an ,

excessive continuous flow demand on the dedicated EFW pump capacity

] required for the system design flow requirements.

1 l Safety Implication:

Failure of the Emergency Feedwater System to provide the total required flow to the steam generators during a loss of normal feedwater event will prevent dissipation of the primary system residual and decay heat within the constraints of the Seabrook Station design analysis.

Corrective Action

4 The EFW pump (s) constant flow recirculation line has been eliminated from the EFW system design. A new Safety Class 3 recirculation line has been installed for each EFW pump. Both recirculation lines return to the condensate-storage tank via a common return header. To ensure the required flow to the steam generators is achievable for all oper-ating conditions, each EFW pump minimum flow recirculation line will

' incorporate a normally closed motor operated valve. Operation of the minimum flow line isolation valves will be administrative 1y controlled from either the main control board or. remote safe shutdown panel, as required.

A complete description of the.EFW System, including the changes i 'made to correct the system deficiencies identified during Hot Functional

}- Testing is provided in FSAR Section 6.8.

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..o United States Nuclear Regulatory Commission Attention: Mr. Richard W. Starostecki Page 3 The prompt, deliberate action undertaken to resolve the EFW System per-formance concerns; the implementation of follow-up corrective actions; and discussions with both Region I and NRR NRC personnel have allowed for an overall thorough evaluation of the EFW system. The proposed modifications will ensure that the minimum required EFW flowrate will be provided to the steam generators for each postulated scenario.

Therefore, it is concluded, that the modified EFW system is capable of performing its intended safety function as delineated in the FSAR.

This letter is being filed as a final 10CFR50.55(e) report.

Very truly yours, A j ohn DeVincentis Director of Engineering cc: Atomic Safety and Licensing Board Service List Director, Of fice of Inspection and Enforcement United States Nuclear Regulatory Commission Washington, DC 20555

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