ML20195F953
| ML20195F953 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 06/09/1999 |
| From: | VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| Shared Package | |
| ML20195F951 | List: |
| References | |
| GL-88-01, GL-88-1, NUDOCS 9906150146 | |
| Download: ML20195F953 (4) | |
Text
I[
Docket No. 50-271 l
BW 99-62*
ATTACHMENT 3 Vermont Yankee Nuclear Power Station l
Proposed Technical Specification Change No. 213 Generic Letter 88-01 and Use of Code Case N-560 Marked-up Version of the Current Technical Specification Pages
- Replaces BVY 9913, Attachment 3 I
9906150146 990609
~~
PDR ADOCK 05000271 P
y
' 3 6.
LIMITING CONDITIONS FOR' 4.6-SURVEILLANCE REQUIREMENTS OPERATION D.
Safety and Relief Valves D.
Safety and Relief Valves 1.
During reactor power' 1.
Operability testing of operating conditions and Safety and Relief Valves whenever the reactor shall be in accordance
)
coolant pressure is with Specification greater than 120 psig 4.6.E.
.The lift point and temperature greater of the safety'and relief than~350*F, both safety.
valves shall be set as valves and at least-specified in three of the four. relief Specification 2.2.B.
valves shall be j
)
2.
If Specification 3.6.D.1 is not met, initiate an orderly shutdown and the
]
reactor-coolant pressure shall be below 120 psig and 350*F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
E.
Structural Inteority and E.
Structural Intecrity and Ooerability Testino coerability Testina l
The structural integrity and 1.
Inservice inspection of the operability of the safety-related j
safety-related systems and components shall be l
components shall be.
performed in accordance maintained at the-level with Section XI of the required by the original ASME Boiler and Pressure acceptance standards Vessel Code and throughout the life of the applicable Addenda as plant.
required by 10 CFR 50, Section 50. 55a (g),
except where specific written relief has been
_q_ ranted by the NRC_.
Inservice inspection or piping, identified.in NRC Generic Letter 88-01, shall be performed in accordance with the staff positions on schedule, methods, and personnel and sample expansion included in 2
the Generic Letter) bel Syf c Se/cc
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GX for & W of Gh A
Ae d n,y y ws/ds ka wM ASMS CA C,.ra 4/. 54 o.
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Amendment No. M, M, 44, GG, Me, MG,160 120 4
et
Docket No. 50-271 BVY 99-62*
ATTACHMENT 4 Vermont Yankee Nuclear Power Station
. Proposed Technical Specification Change No. 213 Generic Letter 88-01 and Use of Code Case N-560 Retyped Technical Specification Pages
- Replaces BVY 99-13, Attachment 4 l
I w-
f:
1 VYNPS i
l 3.6 LIMITING CONDITIONS FOR 4.6' SURVEILLANCE REQUIREMENTS OPERATION D.
Safety and Relief Valves D.
Safety and Relief Valves l
1.
During reactor power 1.
Operability testing of j
operating conditions and Safety and Relief Valves whenever the reactor shall be in accordance coolant pressure is with Specification 4.6.E.
greater than 120 psig and The lift point.of the
(
temperature. greater than safety and relief valves 350*F, both safety valves shall be set as specified and at least three of the in Specification 2.2.B.
l four relief valves shall l
be operable.
1 l
2.
If Specification 3.6.D.1 is not met, initiato an orderly shutdown and the reactor coolant pressure shall-be below 120 psig.
I and 350*F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l l
E.
' Structural Integrity and E.
Structural Integrity and Operability Testing Operability Testing The. structural integrity and 1.
Inservice inspection of the operability of the safety-related components safety-related systems and shall be performed in components shall be accordance with maintained at the level Section XI of the ASME-required by the original Boiler and Pressure acceptance standards Vessel Code and throughout the life of the applicable Addenda as i
plant.
required by 10 CFR 50, l
Section 50.55a(g), except I
where specific written L
relief.has been grantitd t
by the NRC. Inservice inspection of piping, l
identified in NRC Generic l
Letter 88-01, shall be performed in accordance J
with the staff positions on schedule, methods, and personnel and sample
)
expansion included in the Generic Letter, except that sample selection for the scope of Category A welds may be in accordance with ASME Code Case N-560.
l I
Amendment No. M, M, M, M, MB, 4M, MO 120 L: