ML20212J264
| ML20212J264 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 06/24/1999 |
| From: | Alexion T NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| TAC-MA4211, TAC-MA4212, NUDOCS 9906290081 | |
| Download: ML20212J264 (9) | |
Text
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June 24, 1999 MEMORANDUM TO: File FROM:
Thomas W. Alexion, Project Manager, Section 1 ORIG. SIGNED BY Project Directorate IV & Decommissioning Division of Licensing Project Management
SUBJECT:
CLARIFICATION PROVIDED BY THE LICENSEE IN SUPPORT OF RELIEF REQUEST RR-56 (RR-52) (TAC NOS. MA4211 AND MA4212)
By letter dated November 16,1998, as supplemented by letter dated February 23,1999, the licensee submitted Relief Request RR-56 (RR-52) to extend closure exercise test intervals of component cooling water and safety injection check valves. During discussions with the
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licensee, the NRC staff asked for clar.betion of the sentence in its February 23,1999, letter (on page 4 of 7) which states that,"The isolation vaivec in this system are designed to be operated remote-manually from the control room."
In response to the staff's request, and to support additional discussions between the licensee and the staff, the licensee provided the information in the attachment. Th3 purpose of this memorandum is to place the attachment in the Public Document Room.
Docket Nos. 50-498 and 50-499
Attachment:
As stated x DISTRIBUTION:
(Docket Files (50-498 and 50-499)
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June 24, 1999 MEMORANDUM TO: File FROM:
d omas W. Alexion, Project Manager, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management
SUBJECT:
CLARIFICATION PROVIDED BY THE LICENSEE IN SUPPORT OF RELIEF REQUEST RR-56 (RR-52) (TAC NOS. MA4211 AND MA4212)
By letter dated November 16,1998, as supplemented by letter dated February 23,1999, the licensee submitted Relief Request RR-56 (RR-52) to extend closure exercise test intervals of component cooling water and safety injection check valves. During discussions with the licensee, the NRC staff asked for clarification of the sentence in its February 23,1999, letter (on page 4 of 7) which states that,"The isolation valves in this system are designed to be operated remote manually from the control room."
In response to the staff't sequest, and to support additional discussions between the licensee and the staff, the licensee provided the information in the attachment. The purpose of this memorandum is to place the attachment in the Public Document Room.
Docket Nos. 50-498 and 50-499
Attachment:
As stated
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eMAr~>&P8varT WlRJB 1G993UDQAaggRg P.01/07 SOUTH TEXAS PROJECT NUCLEAR OPERATING COMPANY mgh wu
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NUCLEAR LICENSING 7
P. O. Box 289
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l' rom:
Richard Karsey To:
Murr!r, Craig; Scott, Bradley; Walker, Phinp
Subject:
Relief Request CCW CheckValves i discussed with Ken House and Jeff Cottam understanding that we wlu:
Facs the proceeding explanation to Tom Alexlor$
Facs the supporting procedure pages to Tom Alexion (0POPO4RC0006 Shutdown LOCA)
Discuss the issue at 1300 with Tom Alexion, Dave Fisher and STPEGS personnel.
Explanation:
NRR reviewer Dave Fischer reque:ited assurance that the 89-10 MOV program shows the CCW Supply and Retum valves (to RHR HX) win r.bse against an RHR HX tube rupture. The reviewer needs this assurance in his SER which addresses extended interval testing of the CCW check valves.
The reviewer cited the jnservice Testing (IST) Program Bases Document as the source of the tube rupture criteria. The IST Program Bases Document states in part that the CCW Supply /Retum MOVs are required to:
"J. Close (remote manual) in response to a tube rupture in the RHR heat exchanger per UFSAR 8ection 62.4.2.1, item 1.b and leak tight (CAT A) in accordance with UFSAR commitment to provide containmentintegrity".
The answer to the reviewers request is that there is no 89-10 functional requirement for the MOVs to close agamst an RHR HX tube rupture. The UFSAR commitment is that:
The isolation valves in this system are designed to be operated remoto-manually from the control room. (UFSAR 6.2.4.2.1, Special Containment Isolation Provis' ens, llam ib.)
While an RHR HX tube rupture would be detected by the features described in the same UFSAR paragraph (CCWS radiation monitor, CCWS flow Indications, the high and low flow alarms, surge tank level indication, and tank high level alarms) immediate mitigation of the event would utilize plant features other than the CCW MOVs. The procedure for a shutdown loss of coolant event would be utilized to secure the Residual Heat Removal system (s) and therefore secure the leak.
The CCW MOVs would still be able to be remote manus;tly operated (closed) at some time after the event after RHR is secured as determined necessary in the response. Wi:h the tube rupture pressure source secured, the CCW system conditions would not be different with respect to MOV operation. Therefore, the functional criteria for these MOVs to actuate against CCW pressure and flow conditions remains the bounding functional criteria for the MOVs.
CC:
Cottam, Jeffrey; House, Kenneth; Stillwell, Daniel
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SOUTH TEXAS PROJECT NUCLEAR OPERATING COMPANY D0527 amou,.rmwumma.
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OPOP04-RC-0006 Rev.5 Page1of49
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Shutdown LOCA Quality Safety-Related Usage: IN HAND Effective Date: 04/16/98 C. W. Wasek J. Hell Crew 2D operations PREPARER TECHNICAL USER Coon 1ZANT oEPT.
LIST OF ATTACHMENTS:
Addendum 1, RCS Leakage With SI Not Required Addendum 2, Cold Overpressure Limits (Low PORV, PCV-656A)
Addendum 3, Cold Overpressure Limits (High PORV, PCV-655A)
Addendum 4, Saturation Curve Addendum 5, Establishing Containment H2 Monitoring Addendum 6, Phase A Isolation Verification ConditionalInformation Page i
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l This procedure is applicable in Mode 3 with RCS pressure LESS THAN 1000 psig AND in Mode 4.
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26 RAP 8 hl W#eu 7JMLnTUffdiE10Kd P.04/07 0 POP 04-RC-0006 Rsv.5 Page 2 cf 49 Shutdown LOCA PURPOSE This procedure provides necessary operator actions for protecting Reactor' Core in event that a Loss of Coolant Accident (LOCA) occurs during operation in Mode 3 with RCS pressure LESS THAN 1000 psig OR during Mode 4.
j SyMPIOMS AND ENTRY CQ@lTIONS The following symptoms are indicative of a Shutdown LOCAt Uncontrolled decrease in pressurizer level Increasing containment sump levels e
Increasing containment radiation levels (RM11 or RM23) e Increasing MAB or FHB radiation levels (RM11 or RM23) o RCS Subcooling LESS THAN 35CJF without a loss of secondary heat sink e
Increasing containment pressure o
increasing containment temperature o
Increasing. containment dew point o
ADVERSE CONTAINMENT CONDITIONS IE any of the following conditions ne met, THEN USE adverse containment values:
Containment pressure GREATER THAN OR EQUAL TO 5 PSIG.
o Containment radiation levels GREATER THAN OR EQUAL TO 10 PJHR.
5 o
Containment integrated radiation dose GREATER THAN OR EQUAL TO 10' RADS.
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v.wwr-OPOP04-RC-0006 Rsv.'5 P*s' 3 of 49 Shutdown LOCA STEP ACTIONS / EXPECTED RESPONSE RESPONSENOT OBTAINED 1 CHECK ReactorTrip And OPEN Reactor Trip and Bypass Breakers.
Bypass Breakers. OPEN 2 CHECK Letdown. ISOLATED a.
Letdown Orifice Header a.
CLOSE valve.
Isolation Valve FV-0011 -
CLOSED b.
Nonnal Letdown Loop Isolation b.
CLOSE valves.
Valves-CLOSED LCV.0465
=
LCV.0468 c.
Excess Letdown Loop Isolation c.
Cf.OSE valves.
Valves-CLOSED MOV-0082 MOV-0083 d.
Low Pressure Letdown Isolation d.
CLOSE valves.
Valves-CLOSED MOV-0066A MOV.0066B L
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OPOP04-RC-0006 Rev. 5 Page d of 49 '
Shutdown LOCA STEP ACTIONS / EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 CHECK Charging Flow-ADEQUATE a.
CHECK CCP STATUS - ANY a.
START one CCP.
RUNNING b.
CHECK PressurizerLevel:
b.
PERFORM the following:
- GREATERTHAN 8% [44%)
1)
ADJUST Charging Flow Control Valve to maintain Pressurizer level STABLEQR INCREASING OREATER THAN 8% (44%).
e 2)
IE PressurizerlevelcanliQIbe maintained GREATER THAN 8%
[44%) using one CCP,IHEN GO TO Step 4.
c.
CHECK RCS Subcooling.
c.
00 TO Step 4.
GREATERTHAN 350F (450F]
d.
CHECK VCTlevel.LESS d.
PERFORM the following:
j THAN 15%
j 1)
WHEN VCT level decreases to LESS THAN 15%, THEN PERFORM Step 3.e and 3.f.
2)
GO TO Addendum 1.
4 Step 3 continued on next page.
...-a.-.
vaaannstnaams u%#ve OPOP04-RC-0006 Rev.5 Pagc5cf49 Shutdown LOCA i
STEP ACTIONS / EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 3 continued from previous page.
l e.
OPEN RWST to CCP suction isolation isolation valves - OPEN valves.
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1 f.
CLOSE VCT to CCP suction isolation' isolation valves-CLOSED valves.
1 g.
GO TO Addendum 1 4 ESTABLISH High Head SI Flow:
a.
START one HHSIpump i
b.
CHECK HHSI flow-b.
ESTABLISH lineup for HHSI flow.
I INDICATED i
S VERIFY All RHR Trains.
ISOLATED l
a.
CHECK RHR pumps.
a.
SECURE any running RHR pump.
SECURED I
b.
CHECK RHR suction b.
CLOSE RHR suctionisolation valves.
I isolation valves. CLOSED l
TOTAL P.07 l