ML17312B144
| ML17312B144 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/10/1996 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17312B143 | List: |
| References | |
| NUDOCS 9612240300 | |
| Download: ML17312B144 (4) | |
Text
~I -~
~
s $pe IIE00 gO
~+*<<+
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205554001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 110 TO FACILITY OPERATING LICENSE NO. NPF-41 AMENDMENT NO.
102 TO FACILITY OPERATING LICENSE NO.
NPF-51 AND AMENDMENT NO.
82 TO FACILITY OPERATING LICENSE NO.
NPF-74 ARIZONA PUBLIC SERVICE COMPANY ET AL.
PALO VERDE NUCLEAR GENERATING STATION UNIT NOS.
1 2
AND 3 DOCKET NOS.
STN 50-528 STN 50-529 AND STN 50-530
1.0 INTRODUCTION
By application dated June 28,
- 1996, the Arizona Public Service Company (APS or the licensee) requested changes to the Technical Specifications (Appendix A to Facility Operating License Nos.
NPF-41, NPF-51, and NPF-74, respectively) for the Palo Verde Nuclear Generating Station, Units 1, 2, and 3.
The Arizona Public Service Company submitted this request on behalf of itself, the Salt River Project Agricultural Improvement and Power District, Southern California Edison
- Company, El Paso Electric Company, Public Service Company of New
- Mexico, Los Angeles Department of Mater and Power, and Southern California Public Power Authority.
The proposed changes would modify the technical specifications (TS) to increase the minimum required amount of anhydrous trisodium phosphate (TSP) in the containment baskets.
In Surveillance Requirement (SR) 4.5.2.d.2 the amount of TSP used to control pH'f the sump water after a postulated large break loss-of-coolant accident (LOCA) was increased from the previously specified value.
In SR 4.5.2.d.3 the test procedure for determining the rate of dissolution of TSP was modified.
2.0 EVALUATION In order to control pH in the sump water after a postulate large break
- LOCA, the Palo Verde plants are required to store a predetermined amount of TSP in baskets located in the containment sump.
After a postulated
- accident, the stored TSP will dissolve in the accumulated water and keep its pH equal to or higher than seven.
Current SR 4.5.2.d.2 requires the licensee to verify that a minimum of 22,450 pounds (464 ft ) of anhydrous TSP is stored in the baskets.
This amount of TSP, when dissolved in sump water, will produce a
solution containing 3. 1 grams of TSP/liter of water.
- Recently, the licensee found that this concentration of TSP is not sufficient to maintain pH at the required levels.
The licensee recalculated the amount of TSP required, and determined that the minimum required amount of TSP is 25,325 pounds (524 ft )
- which, when dissolved, will produce a concentration of 3.5 grams of TSP/liter.
This concentration of TSP is sufficient to maintain pH above
- seven, assuming a
96X2240SOO 9S<2X0 PDR ADQCK 05000528 P
4l 41 V
This concentration of TSP is sufficient to maintain pH above
- seven, assuming a
maximum concentration of boron in the sump water of 4400 ppm.
The staff evaluated the licensee's results and performed independent calculations.
The staff found the licensee's values to be adequate.
The licen~ee stated in its application that although the current TS specify only 464 ft of TSP, their surveillance testing determined that they majntain TSP stored in the containment sump baskets in excess of 550 ft through administrative controls.
The plant, therefore, has maintained the capability to properly control post-accident pH of sump water.
The licensee revised SR 4.5.2.d.3 which specified the procedure for verifying the dissolution rate of TSP.
The new procedure is more representative of the actual post-accident conditions at which dissolution of TSP takes place.
The licensee changed the 'relative quantities of TSP and water used in the test from one pound of TSP and one gallon of water, to one gram of TSP and one liter of water.
Also, the temperature of water used in the test was changed from 7719'F to 13919'F, which is a more representative value.for the post-accident sump water.
The staff's review concluded that this test procedure is more indicative of actual postulated post-accident conditions, and the modification is therefore acceptable.
3.0 STAT CONSULTATION In accordance with the Commission's regulations, the Arizona State official was notified of the proposed issuance of the amendments.
The State official had no comments.
- 4. 0 NV ONHENTAL CONSIDERATION The amendments change surveillance requirements.
The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released
- offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a
proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (61 FR 47962).
Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
5.0
~CONC US ON The Commission has concluded, based on the considerations discussed
- above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed
- manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
K. Parczewski Date:
December 10, 1996
4i 1,
,'11
~-
acr> l'g 1
Iyf
'J,~,
~