ML17300A918

Suppl 2 to Palo Verde Generating Station Unit 2 Startup Rept.

ML17300A918
Person / Time
Site:	Palo Verde
Issue date:	06/30/1987
From:	ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML17300A917	List: ML17300A916 ML17300A918
References
NUDOCS 8706240329
Download: ML17300A918 (3)

Text

PALO VERDE NUCLEAR GENERATING STATION UNIT 2 STARTUP REPORT (Docket No. 50-529)

Supplement 2 June 1987 870~240329 870hi8 PDR ADOCK 05000529 P PDR

PVNGS UNIT 2 STARTUP TEST REPORT SUPPLEMENT 2 PAGE 1 This is the second supplement to the Startup Report for Unit 2 of the Palo Verde Nuclear Generating Station (PVNGS). The original report, submitted to the U.S. Nuclear Regulatory Commission oa December 19, 1986 (Ref. 1), addressed the startup test phases of Initial Fuel Loading through Power Ascension Testing. This report was followed in March 1987 by Supplement 1 (Ref. 2), which updated the status of the test commitments remaining open from the original report. This supplement addresses the status of the final open test commitment remaining for Unit 2, the Reactor Coolant and Secondary Chemistry and Radiochemistry Test (Startup Report Section 6.5).

REFERENCES

1) Letter ANPP-39447, "Unit 2 Startup Report", dated December 19, 1986, from J.G. Haynes to J.B. Martin

2) Letter 161-00075-JGH/PGN, ."Unit 2 Startup Report; Supplement 1", dated March 13, 1987, from J.G. Haynes to the USNRC Document Control Desk.

PVNGS UNIT 2 STARTUP TEST REPORT SUPPLEMENT 2 PAGE 2 Section 6.5 (CESSAR Section 14.2.12.5.5)

The proper operation of the Process Radiation Monitor (PRM) was not verified during the Power Ascension Testing due to offscale (high) readings above 50'ull power as the result of a higher than expected level of RCS activity. A modification of the PRM has been implemented which reduced the volume of the sample (and thus the local count rate) being monitored, but retesting of the monitor has been delayed due to a broken check valve, located in an associated bypass line, which prevents the proper amount of flow from reaching the PRM. Additionally, a review of the PRM design is being performed to determine the flow rate through the PRM with the check valve operating properly, as this flow is suspected to be far below the specified nominal value. The actual flow through the PRM (with a properly operating check valve) appears to be sufficient to allow the proper indication of RCS activity trends, as evidenced by the successful testing of the Unit 1 PRM. However, too low a flow rate is undesireable due to the increased transit time from the RCS'to the PRM and due to the increased plating out of antimony and other activated corrosion products on the PRM sample tube walls, thereby increasing the background count rate and degrading the monitor sensitivity.

Receipt of replacement parts for the broken check valve in Unit 2 is expected to occur in August 1987, and the valve will be repaired during the first planned outage, which at this time is the first refueling outage scheduled to begin in February 1988.

Additionally, any modifications identified by the design review will be implemented during Unit 2's refueling outage. Following the outagep testing of the PRM will be performed and documented in accordance with the plant administrative procedures controlling plant modifications. This testing will include the test requirements of CESSAR Section 14.2.12.5.5. A summary report will be submitted following the satisfactory completion of testing on the PRM. Therefore, this item is considered closed with respect to the initial startup test program.