ML20207D482
| ML20207D482 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/26/1999 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20207D464 | List: |
| References | |
| NUDOCS 9903090361 | |
| Download: ML20207D482 (7) | |
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. TABLE 4.3-2 (Continued)
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_ TABLE fl0TATI_C_fi (1) The. coincident logic circuits shall be tested automatically or i-man'ually~ at least once per 31 days. The automatic test feature shal.1 be verified OPERABLE at least once per 31 days, y
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4 IGLS'IO!E 1; NIT 2 3/4 3-25 Amendrent No.
J' 9903090361 990226 7 PDR ADOCK 05000 M.:
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INSERT G - Paae 3/4 3-25 The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or other specified conditions for surveillance testing of the following:
a.
Pressurizer Pressure Safety injection Automatic Actuation Logic; and 1
b.
Pressurizer Pressure Containment isolation Automatic Actuation Logic; and c.
Steam Gererator Pressure Main Steam Line isolation Automatic Actuation Logic; and j
- d. '
Pressurizer Pressure Enclosure Building Filtration Automatic Actuation Logic.
Testing of the automatic actuation logic for Pressurizer Pressure Safety injection, Pressurizer Pressure Containment isolation, and Pressurizer Pressure Enclosure Guilding Filtration shall be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after exceeding a pressurizer pressure of 1850 psia in MODE 3. Testing of the automatic actuation logic for Steam Generator Pressure Main Steam Line isolation shall be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after exceeding a steam generator pressure of 700 psia in MODE 3.
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3/4.3 INSTRUNENTATION-BASES
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3/4.3.1 AND 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF) INSTRUNENTATION (continued) ladders, testing one ladder matrix at a time will not remove an RPS channel f
from the overall logic matrix. Therefore, matrix testing will not remove an RPS channel from service or make the RPS channel inoperable.
It is not 1
necessary to enter an actior, statement while performing matrix testing. This also applies when testing the reactor trip circuit breakers since this test will not remove an RPS channel from service or make the RPS channel inoperable.
4 The measureme it of response time at the specified frequencies provicies assurance that the protective and ESF action function associated with each channel is completed within the time limit asumed in the accident analyses.
No credit was taken in the analyses for those channels with response times indicated as not applicable. The Reactor Protective and Engineered Safety Feature response times are contained in the Millstone Unit No. 2 Technical Requirements Manual. Changes to the Technical Requirements Manual require a
.10CFR50.59 review as well as a review by the Plant Operations Review Committee.
The containment airborne radioactivity monitors (gaseous and particulate)
I are provided to initiate closure of the containment purge valves upon detection of high radioactivity levels in the containment. Closure of these valves prevents excessive amounts of radioactivity from being released to the <
l environs in the event of an accident. The actuation logic for this function is 1 out of 4.
Action Statement 3 of Table 3.3-3 addresses inoperable containment purge channels.
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NILLSTONE - UNIT 2 8 3/4 3-la Amendment No.
0306
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INSERT E - Pace B 3/4 3-ia l
The provisions of Specification 4.0.4 are 'not applicable for the CHANNEL FUNCTIONAL TEST of the Engineered Safety Feature Actuation System automatic actuation logic associated with Pressurizer Pressure Safety injection, Pressurizer Pressure Containment Isolation, Steam Generator Pressure Main Steam Line isolation,
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and Pressurizer Pressure Enclosure Building Filtration for entiy irito MODE 3 or other l
specified conditions.. After entering MODE 3, pressurizer pressure and steam generator pressure will be increased and the blocks of the ESF actuations on low l
pressuri2.or pressure and low steam generator pressure will be automatically removed.
t After the blocks have been removed, the CHANNEL FUNCTIONAL TEST of the ESF automatic actuation logic can be performed. The CHANNEL FUNCTIONAL TEST of the ESF automatic actuation logic must be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishing the appropriate plant conditions, and prior to entry into MODE 2.
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i Docket No. 50-336 B1768%
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Millstone Nuclear Power Station, Unit No. 2 l
Additional Modifications to a Proposed Revision to Technical Specifications Compliance issues Number 4 (TAC No. MA3553) l Retyped Pages I
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i February 1999 I
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TABLE 4.3-2 (Continued)
TABLE NOTATION (1) The-coincident logic circuits shall be tested automatically or manually at least once per 31 days.
The automatic test feature shall be verified OPERABLE' at least once per 31 days-The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or other specified conditions for surveillance testing of the following:
a.
Pressurizer - Pressure Safety Injection Automatic Actuation Logic; and b.
Pressurizer Pressure Containment Isolation Automatic Actuation Logic; and c.
Steam Generator Pressure Main Steam. Line Isolation Automatic Actuation Logic; and d.-
Pressurizer Pressure Enclosure Building Filtration Automatic Actuation Logic.
Testing of the automatic actuation logic for Pressurizer Pressure Safety Injection, ' Pressurizer Pressure Containment Isolation, and Pressurizer Pressure Enclosure Building Filtration shall be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after exceeding a pressurizer pressure of 1850 psia in MODE 3.
Testing of the automatic actuation logic for Steam Generator Pressure Main Steam' Line Isolation st di be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after exceeding a steam generator pressure
-of_700 psia in MODE 3.
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o.ILLST0NE - UNIT 2-3/4 3-25 Amendment No. p,
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3/4.3 INSTRMENTATION l
1 BASES 1
3/4.3.1 AND 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES l
(ESF) INSTRUMENTATION fcontinued) i 3
ladders, testing one ladder matrix at a time will not remove an RPS channel j
from the overall logic matrix. Therefore, aratrix testing will not remove an RPS channel from service or make the RPS channel inoperable.
It is not necessary to enter an action statement while performing matrix testing. This also applies when. testing the reactor trip circuit breakers since this test will not remove an RPS channel from service or make the RPS channel inoperable.
The provisions of Specification 4.0.4 are not applicable for the CHANNEL FUNCTIONAL TEST of the Engineered Safety Feature Actuation System automatic actuation logic associated with Pressurizer Pressure Safety Injection, Pressurizor Pressure Containment Isolation, Steam Generator Pressure Main i
Steam Line Isolation, and Pressurizer Pressure Enclosure Building Filtration j
for entry into MODE 3 or other specified conditions. After entering MODE 3, j
pressurizer pressure and steam generator pressure will be increased and the blocks of the ESF actuations on low pressurizer pressure and low steam generator pressure will be automatically removed. After the blocks have been j
removed, the CHANNEL FUNCTIONAL TEST of the ESF automatic actuation logic can i
be performed. The CHANNEL FUNCTIONAL TEST of the ESF automatic actuation
)
logic must be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishing the appropriate
[
plant conditions, and prior to entry.into MODE 2.
3
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The measurement of response time at the specified frequencies provides
~
assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the accident analyses.
i
' No credit was taken in the analyses for those channels with response times indicated as not applicable. The Reactor Protective and Engineered Safety i
Feature. response times are contained in the Millstone Unit No. 2 Technical Requireents Manual.
Changes to the Technical Requirements Manual require a 10CFR50.59 review as well as a review by the Plant Operations Review Committee.
The containment airborne radioactivity monitors (gaseous and particulate) are provided to initiate closure of the containment purge valves upon detection of high radioactivity levels in the containment. Closure of these valves ~ prevents excessive 4. mounts of. radioactivity from being released to the environs in the event of an accident. The actuation logic for this function is 1.out of 4.
Action Statement 3 of Table 3.3-3 addresses inoperable containment purge channels.
e MILLSTONE - INIIT 2 8 3/4 3-la Amendment No. JJ).
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