ML20072P950
| ML20072P950 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 11/16/1990 |
| From: | Greenman E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072P952 | List: |
| References | |
| NUDOCS 9011290340 | |
| Download: ML20072P950 (6) | |
Text
.
' s tic o
+#
o'g UNITED STATES
[\\
p, NUCl.E AR REGULATORY COMMISSION 5-
.j W ASHINGTON, D. C. 20555
/
b e.... '#
DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY 3 hER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE hT!N$i"ko)OPb6 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, et al.
(the licensee) dated October 25, 1990 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter i; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and j
E.
The issuance of this amendment is in acccrdance with 10 CFR Part 51 of.the Comission's regulations and all applicable requirements have been satisfied.
1 l
L l
gi 7,I R.mceco 90,, aADOCK 030993:,4 PDC
2 I
2.
Accordingly, the license is annended by changes to the Technical Specifications as indicated in the attachment to this license i
amendment, and paragraph 2.C.(2) of Facility Operating License i
No. DPR-66 is hereby amended to read as follows:
(2) Techn_ical_ Specifications
)
The Technical Specifications contained in Appendix A, as revised through Amendnient No.
156, are hereby incorporated in the license.
i The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 9
1_
V Edward G. Greenman, Acting Assistant Director i
for Region 1 Reactors f
project Directorate I-4 Division of Reactor Projects - I/11 Office of Huclear Reactor Regulation j
Attachment:
Changes to the Technical i
Specifications Date of Issuance: November 16, 1990 l
l L
i l
N-ATTACHMENT TO LICENSE AMENDMENT NO. 156
- FACILITY OPERATINGLLICENSE NO. DPR-66
-DOCKET NO. 50-334 Replace theLfollowing pages of Appendix A, Technical Specifications, with the
.-enclosed pages as indicated. The revised pages-are. identified by amendment-number-and contain vertical lines indicating the areas of change.
Remove Insert f
3/4 6 3/4 6-6 3/4 6 3/4.6-7
^
3/4 6-14 3/4 6-14 1
~
.t t
!f) i l'
1-l T
i
.-^
' CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (continued) e.
At least once per 18 months during shutdown, by:
1.
Cycling-cae:1 power operated (excluding automatic) valve in the flow path not testable during plant operation, through at least one complete cycle of full travel.
2.
Verifying that each automatic valve in the flow path actuate to its correct position on a test signal.
3.
Initiating flow through each River Water subsystem and its two associated recirculation spray heat gxchangers, and verifying a flow rate of at least 8000 gpm f.
At least once per 5 years by performing an air or smoke flow test.through each spray header and verifying each spray nozzle is unobstructed.
t I
l-I-
I.
l 1The value of 8000 gpm may be lowered to 6000 gpm provided the l
additional operational restrictions
- tmposed by-Figure 3.6-1 of
.L.C.O.
3.6.1.4 are applied.
This provision is only applicable until the eight (8th) refueling outage.
1-*
l l
i BEAVER VALLEY - UNIT 1 3/4 6-14 Amendment No. 91,117 l
F
I I
I i
i i
NOTES:
10.6
- 1. RWST TEMPERATURE BETWEEN 45 'F AND 55 'F.
10.5 2 MAXlMUM ALLOWABLE CONTAINMENT TEMPERATURE 105 'F.
TCEMABR OPMICNi 10.4
- 3. MINIMUM ALLOWABLE CONTAINMERT
)WITH AVAIU(BLE RIVER'!
. \\
AIR PARTML PRESSURE 8.9 PSM.
[NATER FLCiWTO RSS-i x\\
10.3
- 4. MAXIMUM RNER WATER
[ HEAT::EXCH. a:::8000 GPIAj!:
TEMERATuRE so *F T.k 10.2
- .w 10.1 i
\\_t 4~
i 10.0 Y.a a
CONTAINMENT
$k O'8
--\\
TE WPER ATUR E 2: 76 'FsN
\\
UNACCEPTABLE l9.7 f(OPERATION ACCEPTABLE DPERATION wii pVAUBLEF IVER y
g AER MN TO RSS Y
A I*9.6 7
' M
'Y HEAT EXCH, n 6000 GPM *
- l 9.4
.a 9.3 U:
CONTAINMENT TEMPERATURE a: 95 'F %
m:
9.2 9.1 M::
9.0 j
8.9 30 35 40 45 50 55 60 65 70 75 80 85!90 RIVER WATER TEMPERATURE ( *F)
FIGURE 3.61 MAXIMUM ALLOWABLE PRIMARY CONTAINMENT AIR PRESSURE VERSUS RIVER WATER TEMPERATURE
- The 6000 GPM is app!Icable until the eighth refueling outage (8R) only and then reverts to 8000 GPM following 83.
BEAVER VALLEY - UNIT 1 3/4 6-7 Amendment No. 37, 143
CONTAINMENT SYSTEMS INTERNAL PRESSURE l
l LIMITING CONDITION FOR OPERATION l
3.6.1.4 Primary Containment internal air partial pressure shall be maintained 2
8.9 PSIA and within the acceptable operation range (below and to the left of the aoplicable containment temperature limit line(s))
shown on Figure 3'.6-1 as a function of river water temperature.
APPLICABILITY:
MODES 1, 2,
3 and 4.
ACTION:
With the containment internal air partial pressure < 8.9 PSIA or above the applicable containment temperature limit line(s) shown on Figure 3.6-1, restore the internal pressure to within the limits within 1
hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
1 SURVEILLANCE REQUIREMENTS 4.6.1.4 The primary containment internal pressure shall be determined to be within the limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
1 l
i BEAVER VALLEY - UNIT 1 3/4 6-6 Miendment No.143
.