ML20148D123
| ML20148D123 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 10/30/1978 |
| From: | Minnick L YANKEE ATOMIC ELECTRIC CO. |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| WYR-78-92, NUDOCS 7811020246 | |
| Download: ML20148D123 (5) | |
Text
Proposed Change No. 164 Telephone 617 366-9011 f
TWX 700-390-0739
' ~1"-1 YANKEE ATOMIC ELECTRIC COMPANY B.3.2.1 1h 20 Turnpike Road Westborough, Massachusetts 01581
(
AN KEE
's WYR 78-92 October 30, 1978 United States Nuclear Regulatory Commission Washington, D. C.
20555 Attention: Office of Nuclear Reactor Regulation Tgis DOCUMENT CONTAINS Dennis L. Ziemann, Chief POOR QUAUTY PAGES Operating Reactors Branch #2 Division of Operating Reactors
Reference:
(1) License No. DPR-3 (Docket No. 50-29)
(2) YAEC Letter to USNRC, Fire Protection Evaluation Safe Shutdown Methods dated October 16,1978 (WYR 78-89)
(3) YAEC Letter to USNRC, Yankee Rowe Proposed ECCS Recirculation System Modification for Core XIV dated June 6, 1978, Proposed Change No. 160
Dear Sir:
Subject:
Addition of Manual Containment Isolation Valves Pursuant to Section 50.59 of the Comm1ssion's Rules and Regulations, Yankee Atomic Electric Company hereby proposes the following modifications to Appendix A of the Operating License:
PROPOSED CHANGE:
l 1
Reference is made to Operating Licence DPR-3 issued to Yankee l
Atomic Electric Company for the Yankee Rowe plant. We propose to amend the License as follows:
Modify Table 3.G-1 " Containment Isolation Valves" (page 3/4 6-14) to reflect the addition of four manual isolation valves.
REASON FOR CHANGE:
During the site visit of the NRC Fire Hazard Review Team in September, a concern was expressed about the ability to safely shutdown the plant independent of fires in certain specified areas.
t O
A shutdown method independent of the turbine building was of the
[
greatest concern since several areas such as the control room, switchgear y
room, emergency feed pump area and the feedwater control station area are entirely within the boundaries of the turbine building.
2
/2 7871'E oAV4 g
1 United States Nuclear Regulatory Commission October 30, 1978 Att: Office of Nuclear Reactor Regulation Page 2 Yankee Atomic Electric Company (YAEC) addressed this concern and subsequently described the available methods by telecon and in Reference 2.
To further enhance the ability to safely shutdown, independent of the turbine building, YAEC is installing an additional modification during the November refueling outage. This modification consists of a piping interconnection between the new hot leg injection line described in Reference 3 and each steam generator blowdown line. This new inter-connection provides a means of feeding the steam generators independent of the steam generator feed lines in the turbine building, the main feed pumps, and the emergency steam driven feed pump.
It makes a charging pump available to feed the steam generators. Power for each train of safety injection pumps is provided by a separate energency diesel generator making this system independent of any equipment anywhere in the turbine building complex.
Multiple locked valves provide assurance against interference with the normal functions of either the ECCS or the charging system.
BASIS FOR CRANGE:
The new emergency feed lines enter the steam generator blowdown lines upstream of the exist 1ng automatic containment isolation valves.
The four locked valves, therefore, become containment isolation boundaries and as such beceme subject to type C testing in accordance with Appendix J, 10 CFR 50.
For this reason these valves must be added to the list of manual containment isolation valves in the Technical Specifications.
SAFETY CONSIDERATIONS:
As described above, the system being installed will enhance safety by providing an entirely diverse method of feeding the steam generators and cooling the primary plant in the event of a severe fire or other emergency in the turbine building complex. The requested change to the Technical Specifications assures that four of the valves involved in the change, which perform a containment isolation function, are tested and maintained in accordance with the requirements of Appendix J, 10 CFR 50.
These additional testing requirements will not endanger the health and safety of the public. This proposed change has been reviewed by the Nuclear Safety Audit and Review Committee.
FEE DETERMINATION:
This proposed change requires an approval that involves a single safety issue and is deemed not to involve a significant hazards considera-tion. For these reasons, Yankee Atomic Electric Company proposes this change as a Class III Amendment. A paym ent of $4,000.00 is enclosed.
Yankee Atomic Electric Company believes that the Commission's revised fee schedule is illegal, and has petitioned for review thereof to the U. S. Court of Appeals for the Fif th Circuit. Accordingly, the
J United States Nuclear Regulatory Commission October 30, 1978 Att: Office of Nuclear Reactor Regulation Page 2 license fee filed herewith is submitted under protest, and without waiver of the Company's right to contend that it should be refunded in whole or in part.
SCHEDULE OF CHANGE:
1 The modifications described are scheduled to be completed during j
the October-November 3978 refueling outage. Yankee is, therefore, requesting an expeditic,us review and approval of the change.
We trust this information is satisfactory; however, if you desire additional information, please contact us.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY
.~
L. E. Minnick President COMMONWEALTH OF MASSACHUSETTS)
)ss.
COUNTY OF WORCESTER
)
Then personally appeared before me, L. E. Minnick, who, being duly sworn did state that he is President of Yankee Atomic Electric Company, that he is duly authorized to execute and file the foregoing request in the name and on the behalf of Yankee Atomic Electric Company, and that the statem its therein are true to the best of his knowledge and belief.
W f
Armand R. Soucy Notary Public My Commission Expires September 7, 1984 Enclosures 9 R
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TABLE 3.6-1 (Continued) h CONTAINMENT ISOLATION VALVES
-T g~ 1 m?9
^
VALVE NUMBER FUNCTION PLANT OPERATICN ISOLATION TDE C.
>Snual Valves (Cont'd)
(Yes or No)
Seconds CS-CV-215 Fuel Chute Equalizing NA NA CS-CV-216 Fuel Chute Dewatering NA NA Pump Discitarge VD-V-752*
Neutron Shield Tank-Outer Test NA NA VD-V-754*
Neutron Shield Tank-Inner Test NA
~NA BF-V-4-1 Air l' urge Inlet NA NA 2
BF-V-4-2 Air Purge Outlet NA NA cs IIC-V-602 Air Purge Bypass NA NA PU-MOV-543 ECCS Recirculation Yes 50 PU-MOV-544 ECCS Recirculation Yes 50 BF-CV-1000*
SG#1 Feedwater Regulator No 30 BF-CV-1100*
SGil2 Feedwater Regulator No 30 o
BF-CV-1200*
SG#3 Feedwater Regulator No 30 BF-CV-1300*
SG#4 Feedwater Regulator No 30 PR-V-623 Main Coolant IIcise Pressure Gauge NA NA VD-V-1093 SC#1 Emergency Feed (SI)
No NA VD-V-1094 SG#2 Emergency Feed (SI)
No NA VD-V-1095 SG#3 Emergency Feed (SI)
No NA VD-V-1096 SG#4 Emergency Feed (SI)
No NA
- not subject to type C tests 5.
-