ML17206A527
| ML17206A527 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 11/16/1978 |
| From: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7811240209 | |
| Download: ML17206A527 (10) | |
Text
P. O. BOX 013100, MIAMI, FL 33101 gyral/gg
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FLORIDAPOWER 8( LIGHTCOMPANY November 16, 1978 L-78-366 Office of Nuclear Reactor Regulation Attn:
Mr. Victor Stello, Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D.
C.
20555
Dear Mr. Stello:
Re:
St. Lucie Unit No.
1 Docket No.
50-335 Proposed Amendment to Facility Operating License DPR-67 ln accordance with 10 CFR 50.30, Florida Power 6 Light Company herewith submits.three (3) signed originals and forty (40) copies of a request to amend Appendix A of Facility Operating License DPR-67.
The proposed amendment is being submitted to support the extension of the safety in"'ection tanks'ample line to the reactor auxiliary building,sample room during, the April 1979 refueling.
The'elocation of the sampling point to an area outside of the reactor containment',,building will reduce the personnel radiation exposures associated with contain-ment entries.
The proposed amendment is shown on the attached Technical Specification pages bearing the date of this letter in the lower right. hand corner.
Pa e 3/4 6-5 The two proposed containment isolation valves are added to Table 3.6-1, Containment Leakage Paths.
Pa~e 3/4 6-22 The two proposed containment isolation valves are added to Table 3.6-2, Containment Xsolation Valves.
A written safety evaluation i: attached.
FPL has determined that this is a Class XXX amendment in accordance with 10CFR 170.22.
A check in the amount of >4,000 is enclosed.
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Mr. Victor Stello The proposed amendment-has been reviewed by the St. Lucie Plant Facility Review Group and the Florida Power and Light Company Nuclear Review Board.
They have determined that the proposed change does not involve an unreviewed safety question.
I i
'Yours very truly, Robert E. Uhrig Vice President Advanced Systems 6 Technology REU/WAK/dep Enclosures cc:
Mr. James P. O'Reilly, Region XI Harold F. Reis, Esquire
TABLE 3.6-1 CONTAINMENT LEAKAGE PATHS Penetration 7
~Ss tern Makeup ttater Valve Ta Number
= Gate (I-MY-15-1)
Check
( I-V-15-1347)
Location to Containment Outside Inside Service Teste*
Primary Hakeup Mater Bypass Station Air Globe (I-Y-18-947 Globe I-V-10-947 Outside Outside,.
- Station Air Supply Bypass Y
Instrument Air Gate (I-MV-10-1)
Outside Check (I-V-10-957)
Inside Instrument Air Supply Bypass I'0 Containment Purge Containment
- Purge, Butterfly (I-FCY-25-4)
-. Butterfly I-FCV-25-5)
Butte) fly (I-FCV-25-3)
Butterfly I-FCV-25 2)
Inside Outside Inside Outside Containment Purge Exhaust Containment Purge Supply Type C
23 Haste Management
'Component Cooling Component Cooling Globe (Y-6741)
Check (V-6779)
Butterfly (I-HCV-14-7)
Butterfly (X-HCY-14-.1 )
Outside Outside Outside Outside Butterfly (I-HCV-14-6)
. Outside Butterfly (I-HCV-14-2)
Outside Nitrogen supply to SI Tanks RC Pump CH supply RC Pump CH Return Bypass Bypass Dypass
,25 26 28 Fuel Transfer Tube CVCS Sampling Blind Flange Globe (Y-2515}
Glob'e (Y-2516)
Globe (Y-5200)
Globe (Y-6203)
Globe(l-FCV-03-1E)
Globe(X-FCV-03-1F)
Inside Inside Inside Outside Outside Outside Outside Fuel Transfer Letdown Line
~
Reactor Coolant Sample SI Tank Sample Bypass Bypass
. Bypass Bypass
IC:n m
Valve Ta Number 10.. I-FCV-26-1 8, 2 11; I-FCV-26-3-E 4 12.
I-FCV-26-'5 Ec 6 13-I-V00140(1325)
I-V00143(1325) 14.
I-V00139(1322)
I-V00144(1322) 15.
I-V00101(612)
Penetration Number 52a 52b
, 52c 52d 52e TABLE 3.6-2 Continued Function Radiation monitoring Radiation monitoring Radiation monitoring, return ILRT test tap ILRT test tap ILRT pressure connection Testable Ouring Plant 0 eration Yes Yes Yes Yes Yes Yes Isolation Time Sec y-pCv-03-IE 6 D 28 SI Tank Sample HA --Manual Va ve-Isolation time not applicable.
Hay be opened on an intermittent basis under administrative control.
- ~
Normally closed valves - Isolation time not applicable.
Yes HA *~
Valve Ta Number 10.
I-FCV-26-1 5 2 ll'.
I-FCV-26-3 5 4 12.
I-FCY-26-'5 8 6
13.
I-V00140(1325)
I-V00143(1325)
Penetration Number 52a 52b
. 52c 52d TABLE 3.6-2 Continued Function Radiation monitoring Radiation monitoring.
Radiation nionitoring, return ILRT test tap Testable During Isolation
~P1 0
0 t.i li S
Yes Yes Yes Yes 14.
I-V00139(1322 I-V00144(1322) 15.
I-Y00101(612) 52e 54 ILRT test tap ILRT pressure connection Yes Yes r
HA l6.
T.-PCV-03-IE &D'8 SI Tank Sample HA -. Manual Yalve-Isolation time not applicable.
Hay be opened on an intermittent basis under administrative control.
- ~
Hormally closed valves - Isolation time not applicable, Yes Ng A~c
l RE:
ST.
LUCXE UNIT 1 DOCKET NO. 50-335
. SAPLING VALVES SAFETY EVALUATION INTRODUCTION Sampling of the safety injection tanks (SXT) solution is required to meet the SURVEILLANCE REQUXREtKNT of Technical Specification
'4.5.1.6.
The sample tubing from each SIT presently terminates at a sample sink inside the reactor containment building.
To reduce the manhours and personnel radiation exposures associated with contain-ment entries, we plan to extend the SIT sampling lines to the pri-mary sampling room in the reactor auxiliary building.
This proposed
- change, shown in the attached
- sketch, involves the installation of two (2) containment isolation valves at containment penetration number 28.
This evaluation supports the addition of these two pro-posed, containment isolation valves to Tables 3.6-1'nd 3.6-2 of the St. Lucie Unit 1 Technical Specifications.
XI.
EVALUATXON The proposed change is designed as Quality Group B, Seismic Class I and is consistent with the design criteria used in existing systems.
The electrically operated containment. isolation valyes villbe nor-mally closed, fail closed, and will receive a containment isolation signal (CXS) to close.
The CXS will override a manual attempt in the sample room to open these valves.
No single failure of the proposed system would jeopardize plant.
safety.
A tube failure inside containment would be detected by a low level indication for one safety injection tank and/or increased flow rate to sump.
The leakage rate would be.less than 1.5 gpm, allowing sufficient'ime for operator action in accordance with the Technical Specifications.
The single active failure of one contain-ment isolationvalve would be inconsequential and would not cause a
leakage path since the other valve would be op'erable.
'his change involves small diameter (3/8 inch) tubing and valves.
A spare containment tubing penetration will be used.
The proposed two new containment isolation valves vill receive local leak'ate testing.in accordance with Technical Specification 4.6.1.2..
Operability of these valves will be demons'trated by the SURVEILLANCE REQUXRE1KNTS of Technical Specification 4.6.3.1.1.
III.
CONCLUSXONS Routing the SXT sample tubing to the sample xoom will reduce uanhours and personnel exposure associated with SXT sampling.
The proposed change does not increase the probability or consequences of accidents or malfunctions of equipment important to safety and does not reduce the margin of safety as defined in the basis for any Techni-cal Specification.
This change does not involve a significant hazard consideration and there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner.
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STATE OF FLORXDA
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COUNTY OF DADE
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Robert E. Uhrig, being first duly sworn, deposes and says:
That he is a Vice President of Florida Power
& Light Company, the Licensee herein; That he has executed the foregoing document; that the state-ments made in this said document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.
Robert E. Uhrig Subscribed and sworn to before me this day of
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NOTARY PUBLXC, i nd for the county of Dade, State of Florida NOTA' rVS!.!C OTAL Ot Ft.OttlOA t',t tAMS MY COl<9YSS1Ctl
= Ei".P!11M O'ABC'7, t~
Ny commission expires:
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