ML20116L123
| ML20116L123 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 11/12/1992 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-89-04, GL-89-4, TAC-M61257, TAC-M80470, NUDOCS 9211180174 | |
| Download: ML20116L123 (2) | |
Text
'b' r Valley Power Station Shippingport. PA 15077 0 24 (412) 393-5255 Noventae r 12, 1992 Vee President. Nuclear Group U.
S.
Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555
Subject:
Beaver Valley Power Station, Unit No. 1 Docket '
50-334, License No. DPR-66 Testil.
'od for the Safety Injection Accumula Discharge Check Valves In the
" Supplement to Safety Evaluation Dated May 6, 1991 Regarding the Beaver Valley Unit 1 second-Interval Inservice Testing Program for Pumps and Valves (TAC M80470/M61257)" dated January 24, 1992, the Nuclear Regulatory Commission (NRC) concluded that the Beaver Valley Power Station (BVPS) method for verifying full stroke opening of the safety injection (SI) accumulator discharge check valves should be revised to meet either Position 1 or-Position 2 of Generic Letter (GLJ 39-04.
BVPS has evaluated several different m2thods for verifying the fu)1 stroke open capability of the valves.
The method chosen to te used at BVPS Unit 1 during the ninth refueling outage was developed by the Fort Calhoun Station and presented at the ASME/NRC' Pump and Valve Symposium in July 1990 in
>fUREG/CP-0123, page 271.
This method utilizes a reduced pressure blowdown of the SI accumulator tank while monitoring accumulator and reactor coolant system (RCS) pressures and levels.
The pressures and levels are used to calculate a flow coefficient (C )
value.
The C
is compared.to an acceptance y
y criteria C
value calculated using design quantities.
The Fort y
Calhoun method received interim approval from the NRC in a Safety Evaluation Report dated May 5, 1992.
The major physical configuration and test method differences required to perform the check valve full stroke cxercise at BVPS are listed below:
1.
BVPS will perform the test with the fuel in the reactor vessel and the head installed.
The RCS will be' vented through two power operated relief valves or an equivalent area.
2.
BVPS Unit 1
has 12 inch Anchor Darling swing check valves and BVPS Unit 2 has 12 inch Westinghouse valves.
/'
170101
' A
.e 9211100174 921112 7e PDa ADOCK 05000334 p
.v l y:
.bhi 1
Beaver Valley Power Station, Unit Hu. 1 0cchet No. 50-334, License No. DPR-66
- Test) ng' Method f or the Saf ety Injection Accumulator Discharge Check Valves Page 2 3.
Temporary narrow range pressure transducers will be installed on the RCS and accumulators to reduce the gage inaccuracie'.
4.
A temporary wide range level transducer will-be installed on the accumulator.
5.
The stroke time of the motor operated isolation valves at BVPS is approximately 14 seconds.
6.
At
- BVP3, the accumulators are located below the reactor veasel.
Therefore, there is a difference in height between the accumulators' and the reactor vessel's pressure transmitters which will be considered when calculating the flow coefficient.
7.
BVPS is a three loop plant.
The data collection and manipulation methods, however, will be the same.
The acceptance criteria was calculated in a similar manner and are comparable to those developed for Fort Calhoun.
C ACCEPTANCE CRITERIA y
Loon ft. Calhoun Heaver V111ev Unit #1 A
1189 1154 B
1164 1173 C
1131 1181 D
1159 In conclusion, as required by the supplement to Safety Evaluation
- Report, BVPS plans to re<ise the test method used to verify the full stroke open of the SI cecumulator discharge check alves.
The Fort Calhoun test methol with. the above mentioned differences will be used.
Interim approval to.use this methodology during the ninth refueling outage is requested by January 31, 1993.
It interim approval is granted for Unit 1 during the ninth refueling outage and the testing is successful, the same test method will be planned for Unit 2 during the fourth refueling outage.
If you have any questions or comments concerning this issue, please call J.
D. Carl at (412) 393-5235.
Sincerely, h
44' 7 Y
<<f
'T.
D.
Sieber cc:
Mr.
L.
W.
Rosrbach, Sr. Resident Inspector Mr. T.
T.
Martin, NRC Region I Administrator Mr.
A.
W.
De Agazio, Project Manager Mr. M.
L.
Bowling (VEPCO)
-