ML20096F251
| ML20096F251 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 08/23/1984 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Bishop T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| ANPP-30271-TDS, DER-83-30, NUDOCS 8409070345 | |
| Download: ML20096F251 (5) | |
Text
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s>1 Arizona Public Service Company August 23, 1984 ANPP-30271-TDS/IRB
'U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, - CA 94596-5368 Attention: Mr. T. W. Bishop, Director Division of Resident
-Reactor Projects and Engineering Programs i
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Subject:
Final Report - DER 83-80 A 50.55(e) Reportable Condition Relating To Main Feedwater Isolation Valves Closed In 20 Seconds; Specification Requires 5 Seconds.
File: 84-019-026; D.4.33.2
Reference:
A) Telephone Conversation between P. Narbut and K. Parrish on November 23, 1983 B) ANPP-28462, dated December 19, 1983 (Interim Report)
C) ANPP-28800, dated February 6,1984 (Time Extension)
D) ANPP-28980, dated March 2, 1984 (Time Extension)
E) ANPP-29178, dated March 28, 1984 (Time Extension)
F) ANPP-29581, dated May 23, 1984 (Interim Report)
G) ANPP-29975, dated July 16, 1984 (Time Extension)
Dear Sir:
Attached is our final written report of the deficiency referenced above, which has been determined to be Not Reportable under the requirements of 10CFR50.55(e).
Very truly yours, kO E. E. Van Brunt, Jr.
APS Vice President Nuclear Production ANPP Project Director N'IA l'.'0l993 EEVB/TRB/nj Attachment jg "N LE [f;j N0l cc: See Page Two D!!il e49g7g5j4g2 03,1f33;p j
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Institute of Nuclear Power Operations 1100 circle 75 Parkway, Suite 1500 Atlanta, GA 30339 l
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FINAL REPORT.- DER 8 3-80 DEFICIENCY EVALUATION 50.55(e)
ARIZONA PUBLIC SERVICE COMPANY (APS)
-p PVNGS UNITS 1, 2, 3
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Description of Deficiency
%f CESSAR,' Chapter 5.1.4,Section I.9, specified a 5-second i kr -
closing time for the Feedwater Isolation Valvves (FWIV), and the Final Safety Analysis Report commits to meet this
,4 requirement. This requirement is necessary to limit the mass of water added to the steam generators following a main steam line break (MSLB) inside the containment. Any water admitted c _A b to the steam generator during such an MSLB will be converted t4.
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to steam and released into the containment, thereby increasing the post-accident pressure and temperature. During startup
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testing, it was discovered that the closing time for the Feedwater Isolation Valves exceeded 5 seconds. Startup issued NCR SM-3168 to document this condition.
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The hydraulic actuator of one valve (1JSGB-UV-137) was returned to Anchor Darling and installed on a test rig where w
closing time tests were performed under simulated operating u-s conditions. The minimum closing time attainable was 4
7.3 seconds, and this was obtained with the following actuator g
adjustments:
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"~ l (a) nitrogen charge increased from 3400 peig to 3500 psig at 70*F, and
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,D (b) the setting of the "G" closing speed control valve changed from a 3/4 turn from full closed position to fully open.
To provide margin for closure time variability and allow for f;
degradation over the 40 year plant life, a 10-second or less closing time requirement was specified for licensing purposes.
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To preclude the initiation of various e
pressure / temperature / flow transients associated with fast closure under full flow operating conditions, the fast closure
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,1 4, j' testing at the PVNGS will be static. Anchor Darling has 4
specified a 2-second differential time adjustment for field q
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testing with static ambient water. Therefore, an 8-second or A
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1ess closing time for field testing meets the licenair.g requirement of 10 seconds (BPC Telex MIC #226667, ADVC Telex MIC #226669, and BPC Telex MIC #226668).
To evaluate the consequences of the deviation from the CESSAR interface requirement for FWIV closure time of five.
(5) seconds to ten (10) seconds, Combustion Engineering (C-E) provided'PVNGS-specific mass / energy release data for the design basis main steam line break (MSLB) inside containment assuming a 10-second closure time (Letters V-CE-30008, dated u
March 30, 1984; V-CE-30051, dated April 10, 1984; V-CE-30177, dated May 1,1984; and V-CE-30370, dated June 11, 1984).
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- Mr. T. W. Bishop
.Page Two Bechtel engineering performed a containment pressure-temperature response analysis using the new data from_
C-E and verified that:
(a) the containment temperature profile is enveloped by the equipment qualification thermal profile previously established using generic main steam line break (MSLB) bicwdown data from CESSAR-F, and (b) the peak containment pressure is also bounded by the existing loss-of-coolant-accident (LOCA) environmental qualification envelope.
C-E reanalyzed the limiting MSLB with a 10-second closure time for impact on reactor core thermal-hydraulic response and off-site radiological releases (Letter V-CE-30263, dated May 21,1984). Their analysis confirms that a 10-second closure time will not pose a problem with post-trip return to power, core protection, or off-site radiological releases..
II.
Analysis of Safety Implications During the origina1' Acceptance Tests performed at the manufacturer's facility under simulated operating conditions, the closing time for each valve was checked six (6) times, and the maximum time-to-close was as follows:
Tag No.
Max. Time Tag No.
Max. Time Tag No.
Max. Time-1JSGA-UV-174 - 8.20 sec.
2JSGA-UV-174 - 8.76 sec.
3JSGA-UV-174 - 9.35 sec.
1JSGA-UV-177 - 8.19 sec.
2JSGA-UV-177 - 8.88 sec.
3JSGA-UV-177 - 9.09 sec.
1JSGB-UV-132 - 9.00 sec.
2JSGB-UV-132 - 8.63 sec.
3JSGB-UV-132 - 8.65 sec.
1JSGB-UV-137 - 7.79 sec.
2JSGB-UV-137 - 8.81 sec.
3JSGB-UV-137 - 8.67 sec.
All the valves had closing times less than ten (19) seconds
'during the original acceptance tests, and analysis confirmed that,.for a 10-second closing time, peak containment environmental conditions are enveloped by previously specified values for equipment qualification and that reactor core performance and off-site radiological releases remain within-acceptabla limits. Therefore, the condition herein is evaluated as not reportable under 10 CFR Part 50.55(e) and Part 21 since, if left uncorrected, it would not have constituted a significant deficiency or substantial safety hazard.
III.
Corrective Action-l
- 1. By copy of this DER, Anchor Darling is directed to revise FWIV Instruction Manual No. E9023-9 to reflect the following corrective actions:
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'./f _ f. Mr. T. W. Bishop ANPP-30271-TDS/TRB Page Three e-
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a.
Closing Speed Control Valve "G" on the FWIV actuator s
will be set in fully open position.
b.
The FWIV will be precharged with nitrogen at a pressure of 3500 psig and a temperature of-70* F.
- 2. Safety Analysis Report Change Notice No.1174 has been issued to reflect a 10-second closing time requirement for the FWIV.
3.-For field testing with water in the line at stagnant ambient temperature and zero gauge pressure, but no flow, the specified closing timeushall be 8 seconds or less. The test results shall be documented per Test Procedure 91-HF-1SG01.
The above corrective action is consistent with the final disposition of NCR SM-3168, and is effective for all three units.
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