ML20211N501

Submits Supplemental Response to IE Bulletin 83-05 Re Pump Performance Testing for Pumps Mfg by Hayward-Tyler.Test Results for Runout Flow Conditions for Pump 1SX04P & Normal & Runout Flow Conditions for Pump 2SX04P Encl

ML20211N501
Person / Time
Site:	Byron
Issue date:	12/12/1986
From:	Hunsader S COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
IEB-83-05, IEB-83-5, NUDOCS 8612180240
Download: ML20211N501 (5)

Text

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• .* (s 7 Address Reply to: Post Omco Box 767

\ Chicago,IEnois 60690 0767 December 12, 1986 Mr. James G. Keppler Regional Administrator U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL. 60137

Subject:

Byron Station Units 1 and 2 Supplemental Response to IE Bulletin No. 83-05 on Hayward-Tyler Pumps NRC Docket Nos. 50-454 and 50-455

Reference:

(a) IE Bulletin No. 83-05 R.C. DeYoung letter to All OLs and cps dated May 13, 1983 (b) August 12, 1983 P.L. Barnes letter to J.G. Keppler (c) January 10, 1984 P.L. Barnes letter to J.G. Keppler (d) Inspection Report No. 50-454/86-040 dated November 25, 1986 l (e) Inspection Report No. 50-455/86-040 dated November 18, 1986 (f) Facility Operating License NPF-60

Dear Mr. Keppler:

Reference (a) required licensees to conduct pump performance testing for ASME Nuclear Code pumps manufactured by the Hayward Tyler Pump Co. and provide the test results to the NRC.

Reference (b) informed the NRC that Byron Station had two Hayward Tyler pumps identified as Essential Service Water Booster Pumps 1SXO4P and 2SX04P. Commonwealth Edison provided the test results, at " normal" conditions, for 1SXO4P, via reference (c).

Reference (d) identified that Byron Unit 1 auxiliary feedwater (AF) preoperational test AF2.3.60 for 1SXO4P had not taken performance test data for the minimum and runout flow conditions as required by reference (a). Also the required pump rundown was not observed when the pump was stopped. Commonwealth Edison committed to perform the appropriate tests as a part of the next scheduled surveillance test and submit the results to the NRC.

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Reference (e) identified that Byron Unit 2 AF pre-operational test AF 2.3.60 for 2SXO4P had obtained pump data at

" normal" flow but not at the runout and minimum flow conditions as required by reference (a). To address this item, Commonwealth Edison committed to complete the appropriate retesting as a part of AF retest R-2088. Reference (e) requires that the testing data be provided to and. reviewed by the NRC prior to entering Mode 3.

Attachment "A" provides the supplemental performance test results for both 1SXO4P and 2SX04P, for the runout flow (ISXO4P) and the normal and runout flow (2SXO4P) conditions.

As discussed in reference (d), some conditions are not able to be tested for each pump per Attachment 2 of reference (a). These are presented below and should not be considered as certification requirements for Byron Station's specific application of the Hayward Tyler pumps.

1. " Running current" (Attachment 2, B.4)-This requirement is not applicable si'nce the Byron pumps are diesel driven.

2. " Pump minimum flow"-The jacket-water cooling system for the diesel engine is supplied by the pumps themselves. Inadequate heat removal could occur at the minimum flow condition, resulting in engine overheating and subsequent damage.

3. " Rundown check"-Because the pumps are diesel driven, upon shutdown of the diesel engines (and the pumps) they stop essentially immediately. A rundown test cannot be performed for the Byron Station application.

i To the best of my knowledge and belief, the statements contained above are true and correct. In some respect these statements are not based upon my personal knowledge but upon information furnished by other Commonwealth Edison employees, contractor employees, and consultants. Such information has been reviewed in accordance with Company practice and I believe it to be

reliable.

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Please address any question concerning this response to this office.

One signed original is being sent directly to the U.S.

Nuclear Regulatory Commission Document Control Desk in Washington for reproductions and distribution as requested in the Bulletin.

Very truly yours, l

{f C. Hunsader M

Nuclear Licensing Administrator

/klj cc: US NRC Document Control Desk Washington, DC. 20555 SUBSCRIBED and SWORN to l beforg me th}s /St# day l of /Mc #mt EtEl ) , 1986 11/U N2. ClM/?4Le Notalt{f Public b" 2515K

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ATTACHMENT A Byron Station Units 1 and 2 Performance Test Results Essential Service Water Pumps ISXO4P and 2SXO4P 1SK04P On Unit 1, additional testing was performed at runout flow conditions under Special Procedure 86-164. The data is as follows:

Suction Pressure 58 PSIG Discharge Pressure 68 PSIG Bearing Temperature lO2.80F Ambient Temperature 70.20F SX Inlet Temperature 65.70F Runout Flow 854 GPM Vibration Signatures Acceptable Seal Leakage None Upon review, all test data taken at runout flow was found acceptable. This data was taken after approximately thirty minutes of pump run time. Actual pump discharge flow greatly exceeded pump curve data predictions. This was considered acceptable for this particular pump testing configuration.

2SXO4P A. Test results taken for Unit 2 normal flow conditions in Pre-operational test 2.03.60 are as follows:

Suction Pressure 77 PSIG Discharge Pressure 122 PSIG Flow Rate 435 GPM Vibration Signature Acceptable Boaring Temperature 1040F Ambient Temperature 760F These results were found to be acceptable by the Commonwealth Edison test Review Board (TRB) and Project Engineering Department (PED) as performed during the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> diesel-driven auxiliary feedwater pump performance test.

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-2 B) For Unit 2 additional test data at pump runout conditions was obtained during rotest R-2088, based on AIR 6-86-2210.

This data was taken after approximately thirty minutes run time and is as follows:

Suction Pressure 72 PSIG Discharge Pressure 80.5 PSIG Flow (runout) 912 GPM Vibration Signature Acceptable Bearing Temperature 840F Ambient Temperature 700F Leakage None The results were reviewed and approved by the TRB and PED.

2515K

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