ML19332C393

Forwards Proprietary Temporary Change 1 to Suppl 8 of Rev 34 to Procedure/Work Plan 1104.02, Makeup & Purification Sys Operation, Per 891110 Request for Addl Info Re Amend to Increase Reactor Power Level.Encl Withheld (Ref 10CFR2.790)

ML19332C393
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/21/1989
From:	James Fisicaro ARKANSAS POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19293A031	List: ML19332C393
References
1CAN118905, NUDOCS 8911280067
Download: ML19332C393 (4)

Text

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November 21, 1989 L1CAN118905 U. S._ Nuclear, Regulatory Commission Document Control Desk Mail-Station P1-137

. Washington, DC 20555 k

Subject:

Arkansas Nuclear One - Unit 1 Docket No. 50-313 E License No. DPR-51 Additional Information Related to License Amendment to Increase Reactor Power. Level to 100% Full Power Gentlemen:

During a telephone conversation on November 10, 1989 between the ANO-1 NRC Project Manager, Mr. Craig Harbuck and other members of the NRC staff and Mr. Dale-James' and members of AP&L's Design Engineering organization, we

discussed tne post-modification testing which would be performed following the installation of the cavitating venturis in the High Pressure Injection

'(HPI) system:as described in our-' letter dated' September 26, 1989 (1CAN098903). This letter is provided as a follow-up to that conversation

-and to provide you with a draft copy of the test procedure which will be utilized to perform the post-modification testing. This procedure will be

. finalized within the next two weeks.

.As a result of further development of the design change to install the  !

cavitating venturis, it was determined that the venturi in the "D" HPI line .I should be located downstream of the makeup line tie-in as opposed to upstream as depicted in our figure transmitted to you with our' letter of September 26, 1989. By placing the venturi at this location, the failure of  !

CV-1234 to close will have no substantial effect on the HPI flow delivered i' to the core for a small break that would divert the "D" HPI line flow from the RCS. A revised figure is attached showing the new venturi location.

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After installation of the cavitating venturis, system flow testing will be I performed in order to verify the performance of the modified HPI system using HP.I pump P36A (i.e., the HPI pump with the lowest head-vs-flow curve). l This test will be performed utilizing Procedure 1104.02 as revised by ,

Temporary Change #1. A draft procedure is attached for your information. l In accordance with that procedure, two tests will be performed as discussed in our September 26, 1989 letter to simulate system performance for a small break and an HPI line break. Simulating a small break will test the flow ,

distribution for the modified HPI system for the range of RCS pressure from zero to approximately 600 psig. The venturis are designed to cavitate at RCS pressures below 600 psig such that system flow is not affected by AMI 8911280067 891121 i '

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U. S. NRC Page 2 November 21, 1989 variations in backpressure below this value. In simulating an HPI line break, the second test will demonstrate system performance for an RCS pressure of 1200 psig assuming one broken HPI line downstream of the venturi. An RCS pressure of 1200 psig is representative of the pressure at which the RCS stabilizes following the rapid depressurization immediately after that type of event.

The tests will be performed conservatively with one HPI train available. ,

Since P36A is known to produce less flow than pumps P36B or P36C, it will be l used during the test. HPI train A will be utilized to properly account for the potential ef fect of the makeup line. In order to avoid inventory changes in the RCS, the test will be performed in the " piggyback" mode with j the_HPI pump suction supplied by a Low Pressure Injection (LPI) pump. The LPI pump will take suction from the RCS. Since the HPI pumps would take suctiun from the Borated Water Storage Tank (BWST) during an injection event, the recirculation from the LPI pump will be adjusted in accordance with Step 2.21.12a of the procedure until the suction pressure at the HPI pump is equal to the head pressure from the BWST.

The data collection portion of the testing is described in Attachment U of the test procedure (part of TC #1). The first portion of the test is to ,

simulate a cold leg SBLOCA with RCS pressure from 0 to 600 psig. After stationing personnel at the appropriate locations (Step 1 of Attachment C to the procedure), CV-1220 will be opened (CV-1219 will have been opened in Step 2.21.23a) and data will be collected as directed in Step 3 of  :

Attachment C of the procedure. The characteristics of the system with cavitating venturis installed are such that cavitation will occur at RCS pressures at or below 600 psig. While the venturis are cavitating, the flow is not affected by changes in the downstream pressure. Therefore, although this test is performed at RCS conditions less than 600 psig, it is representative of RCS conditions from 0 to 600 psig.

The next portion of the testing was designed to obtain data at an additional

-point on the pump curve. CV-1220 will be closed to reduce flow and additional data will be collected per Attachrrent C, Step 5 of the procedure.

To simulate an HPI line break, the manual isolation valves will be throttled in three of the injection lines downstream of each respective venturi until the pressure at the gauge upstream of the valves corresponds to an RCS pressure of 1200 psig. The flows and pressures will be recorded (Steps 6 through 10 of Attachment C of the procedure). The procedure is being modified to require throttling of the three lines with the most limiting flow. The test procedure will also be revised to include the potential effect of the makeup line. If, from the first portion of the test, the maximum flow occurs in the "D" HP1 line, the makeup valve (CV-1234) will remain open during the next portion of the test to assure maximum flow out this simulated broken line. If the maximum flow does not occur in "D" line, the makeup valve will be closed during this portion of the test to assure the most conservative flow into the core.

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U. S. NRC Page 3 November 21, 1989 Additional data points will be recorded as needed at different flows to determine the pump performance. This activity.is carried out in Steps 11 and 12 of Attachment C to the procedure.

After the flow test is completed, the venturis will be hydrotested by closing the downstream gate valve in three of the lines and adjusting the flow through the fourth -line to obtain the correct hydro pressure on the system. After testing for 10 minutes, the fourth venturi will be tested in a similar manner (Steps 13 through 31 of Attachment C to the procedure).

Acceptance Criteria The objective of the post-modification test is (1) to verify that the flow 7

to the core exceeds the minimum required as determined by B&W (NSSS Vendor)

L to ensure the SBLOCA analysis remains bounding for ANO-1 based on a licensed l

full power level of 2568 MWt and (2) to establish current perfonnance relative to a Section XI reference curve for the HPI pump to assure an ,

adequate baseline for future testing.

Table 1 (IA and IB) depict the minimum required flows for ANO-1 at 100%

licensed power to be met during the post-modification testing, where Table 1A values result from the B&W analysis -of the spectrum of SBLOCA and Table IB values are for the specific case of an HPI line break.

As calculated,' these flow rates correspond to the flow which reaches the reactor core through the intact flow paths, not total pump flow. Also, the "RCS Pressure" identified in these tables corresponds to the RCS pressure at the HPI nozzles.

B&Wcalculationsestablishedaminimumpumpcurve(Table 2)fortheHPI pump, which corresponds to minimum system performance for compliance with the safety analysis. Since ASME Section' XI allows pump degradation to 90%

of the reference curve before the pump is declared inoperable, the reference curve must be 100/90 of the minimum performance curve.

The results of this flow test will be evaluated to assure the minimum flow values given in Table 1 are achieved for their corresponding RCS pressures and to verify that the system performance corresponds to pump performcnce as predicted by the B&W calculations and that the present pump performance excceds 93% of the reference curve.Section XI allows operation with pump degradation between 100% and 90%; however, between 93% and 90%, increased surveillance would be required.

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U. S. NRC Page 4 November 21, 1989 .

The acceptance criteria provided in Tables 1A and IB and the pump performance curve data of Table 2 were derived by B&W and are considered by them to be proprietary information. Per 10CFR2.790 an affidavit explaining why they consider this information to be proprietary will be provided by B&W under separate cover. A non-proprietary version of this letter is attached for public disclosure.

If you have any questions regarding this information, please do not hesitate to contact me.

Very truly yours, w ..}ai. "

James . Fisicaro Manager, Licensing JJF/TRP/fc Attachments-cc: Mr. Robert Martin U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 NRC Senior Resident Inspector Arkansas Nuclear One - ANO-1 & 2 Number 1, Nuclear Plant Road Russellville, AR 72801 Mr. C. Craig Harbuck NRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-D-18 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 Mr. Chester Poslusny NRR Project Manager, Region IV/AN0-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-0-18 One White Flint North 11555 Rockville Pike Reckville, Maryland 20852