ML20214R729
| ML20214R729 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 09/19/1986 |
| From: | Julie Ward SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| JEW-86-390, TAC-61869, NUDOCS 8609290261 | |
| Download: ML20214R729 (3) | |
Text
f e-kSMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street. P.O. Box 15830, Sacramento CA 95852-1830.(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA JEW 86-390 September 19, 1986 DIRECTOR OF NUCLEAR REACTOR REGULATIONS ATTN J F STOLZ DIRECTOR PWR PROJECT DIRECTORATE #6 DIVISION OF PWR LICENSING-B U S NUCLEAR REGULATORY COMMISSION WASHINGTON DC 20555 DOCKET N0. 50-312 LICENSE NO. DPR-54 PROPOSED AMENDMENT N0. 148, REPLY TO INQUIRIES This letter is in response to your request for additional information dated August 6, 1986 with respect to Proposed Amendment No. 148. This proposed amendment, submitted June 13, 1986, requests NRC approval to change the wording of Technical Specification 4.8.1A which will permit testing of the AFW pump during conditions of either plant operation or shutdown.
The information requested by the NRC and the District's responses are presented on the attached.
Should you require any further information with respect to Proposed Amendment No. 148, please contact Mr. Ron W. Colombo at Rancho Seco Nuclear Generating Station Unit No. 1.
J ARD UTY GENERAL MANAGER NUCLEAR Attachments Subscribed and sworn to before me this l'll day of'c3 a c.. A 1, 1986.
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ATTACHMENT Presented below, in the order submitted, are the District's responses to NRC's request of August 6, 1986 for additional information with respect to Proposed Amendment No. 148:
REQUEST 1.
Confirm that only one AFW pump is being tested at any given time during L
power operation.
RESPONSE
The sequence of verification testing the AFW pumps as performed in accordance 1
with Maintenance Procedure I.032 is such that only one pump is tested at a time.
REQUEST 2.
Describe the means provided to assure that the main feedwater discharge pressure switch root and drain valves are returned to their normal operating position after testing is completed.
In accordance with the criteria of Recomendation GS-6 of NUREG-0611 and -0635 which was implemented under Item II.E.1.1 of NUREG-0737, procedures should be provided which specify dual operator verification of proper valve position upon system restoration.
RESPONSE
The same maintenance procedure as referenced above (I.032) requires independent dual verification that 1) the applicable main feedwater discharge pressure switch isolation valve is closed during the test; 2) that the sensing line is bled, and 3) that at completion of the test, the pressure switch. isolation valve is returned to its normal open position.
REQUEST 3.
Verify that performance of the AFW system actuation test at power will not result in adverse effects to the system. Consideration should bc given to assuring that the AFW discharge line check valves will properly reseat and operation of the AFW pump with the steam generators at normal aperating pressure will not result in pump damage (i.e., dead heading will not occur).
Also confirm that the introduction of cold AFW flow at power will not result in a transient condition affecting plant operation.
RESPONSE
l Dead _ heading the AFW pumps during low flow testing is avoided by directing flow from each pump discharge to the LP condenser through a 21-inch miniflow l
l line.
Isolation of each miniflow line is controlled by a locked-open valve.
When testing the AFW pumps at full flow conditions, each AFW pump discharges through a common 6-inch line, also to the LP condenser in accordance with Surveillance Procedures SP 210.01A and.01B.
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. Integrity and full stroke testing of the check valves are performed quarterly or after refueling or other cold shutdowns of over 30 days duration in accordance with Surveillance Procedures SP 210.011 and.01F, respectively.
Testing of the AFW pumps in accordance with SP 210.01A and.01B procedurally requires the AFW system to be in SFAS standby mode which, per Operating Procedure A.51, has both OTSGs isolated from the AFW system.
Introduction of cold flow from the AFW system to the OTSG and any resulting transient condition is prevented by normally closed automatic opening valves.
REQUEST 4.
Evaluate the effects of the periodic thermal shock on the integrity of the steam generators including the shell, nozzles, and tubes which results when the relatively cold water is injected into the steam generator-during the AFW system test with the plant at power.
Indicate the effect of the proposal on the thermal cycling design margins over the life of plant.
RESPONSE
As indicated in (3.) above, testing of the AFW pumps procedurally requires pump discharge to be to the LP condenser, and for the OTSGs to be isolated from the AFW system. Therefore, thermal shock of the OTSG does not occur.
5.
Confirm that the proposed technical specification change will not preclude performance of the AFW system flow path verification test which is to be accomplished prior to startup after an extended cold shutdown (such as a refueling outage) as identified in Recommendation GS-6 of NUREG-0611 and
-0635.
RESPONSE
In accordance with Surveillance Procedure SP 210.01F, AFW flow rate and flow path verification are performed quarterly or following any refueling shutdown or any cold shutdown of longer than 30 days duration.
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