ML20199H250: Difference between revisions

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Encl'osure 3 4                                                                                               #
Encl' sure 3 o
          .NRC-98-0006 Page1 ENCLOSURE 3 FERMI 2 NRC DOCKET NO. 50-341 OPERATING LICENSE NPF-43 Rri UEST TO REVISE TECIINICAL SPECIFICATIONS:
4
.NRC-98-0006 Page1 ENCLOSURE 3 FERMI 2 NRC DOCKET NO. 50-341 OPERATING LICENSE NPF-43 Rri UEST TO REVISE TECIINICAL SPECIFICATIONS:
TECIINICAL SPECIFICATION Cll ANGE Attached is a mark-up of the existing Technical Specifications (TSs), indicating the proposed changes, (Part 1) and a typed version of the TSs incorporating the proposed changes with a list ofincluded pages (Part 2).
TECIINICAL SPECIFICATION Cll ANGE Attached is a mark-up of the existing Technical Specifications (TSs), indicating the proposed changes, (Part 1) and a typed version of the TSs incorporating the proposed changes with a list ofincluded pages (Part 2).
9002040451 900128 PDR     ADOCK 05000341 P                     PDR
9002040451 900128 PDR ADOCK 05000341 P
PDR


Enclosure 3 NRC-98-0006
NRC-98-0006 Page 2 5
,            Page 2 g     5 ENCLOSURE 3-PART1 PROPOSED TECIINICAL SPECIFICATION PAGE MARK-UP
g ENCLOSURE 3-PART1 PROPOSED TECIINICAL SPECIFICATION PAGE MARK-UP
                                                              .        . _ . _                                                                    _ _ _ _ _ - - _ _ _ . _ _ .J
.J


  *-                                                                                        E/JCl uiO C' & .5 N 2 0.- 4 7- 00 6 7 PR 6. G- 7.-h
E/JCl uiO C' &.5 N 2 0.- 4 7- 00 6 7 PR 6. G-7.-h eel.ll56 REACTOR COOLANT SYSTEM 24
          .,                                                          eel.ll56 REACTOR COOLANT SYSTEM                           24
~
        ~
SURVEILL ANCE REOUIREMENTS (Continuer" l
SURVEILL ANCE REOUIREMENTS (Continuer"
4.4.3.2.2 Each reactor coolant syst' ressure isolation valve specified in Table 3.4.3.2-1 shall be demonstrat PERABLE by leak testing pursuant to Specification 4.0.5 and verifying e leakage of each valve to be within the specified limit:
                                                    !                                                              l 4.4.3.2.2 Each reactor coolant syst' ressure isolation valve specified in Table 3.4.3.2-1 shall be demonstrat     PERABLE by leak testing pursuant to Specification 4.0.5 and verifying e leakage of each valve to be within the specified limit:
a.
: a. At least once pe -16 months, and
At least once pe -16 months, and b.
: b. Prior to returning the valve to service following maintenance, repair or replacement work on the valve which could affect its leakage rate..
Prior to returning the valve to service following maintenance, repair or replacement work on the valve which could affect its leakage rate..
The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 3.
The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 3.
4.4.3.2.3 The high/ low pressure interface valve leakage pressure monitors shall be demonstrated OPERABLE with alarm setpoints per Table 3.4.3.2-2 by performance of a:                               -
4.4.3.2.3 The high/ low pressure interface valve leakage pressure monitors shall be demonstrated OPERABLE with alarm setpoints per Table 3.4.3.2-2 by performance of a:
: a. CHANNEL FUNCTIONAL TEST at least once per 31 days, and
a.
: b. CHANNEL CAllBRATION at least oate per 18 months.
CHANNEL FUNCTIONAL TEST at least once per 31 days, and b.
FERMI - UNIT 2                     3/4 4-11a                                       Amendment No.89
CHANNEL CAllBRATION at least oate per 18 months.
FERMI - UNIT 2 3/4 4-11a Amendment No.89


.          Enclosure 3
. NRC 98-0006 Page 3 ENCLOSURE 3-PART2 PROPOSED TECIINICAL SPECIFICATION REVISED PAGES c
          . NRC 98-0006 Page 3 ENCLOSURE 3-PART2 PROPOSED TECIINICAL SPECIFICATION REVISED PAGES c
3/4 4-11a
3/4 4-11a
                                                                  - - - - -        -u
-u


-4
-4
    - .
* REACTOR COOLANT SYSTEM SURVEILLANCE RE001REMENTS fContinued) 4.4.3.2.2 Each reactor coolant system pressure isolation valve spheified in Table 3.4.3.2-1 shall be demonstrated OPERABLE by leak testing = pursuant to-Specification 4.0.5 and verifying the leakage of each valve to be within-the specified limit:
* REACTOR COOLANT SYSTEM                                                                 -
a.-
SURVEILLANCE RE001REMENTS fContinued) 4.4.3.2.2 Each reactor coolant system pressure isolation valve spheified in Table 3.4.3.2-1 shall be demonstrated OPERABLE by leak testing = pursuant to-Specification 4.0.5 and verifying the leakage of each valve to be within- the specified limit:
At least once per 24 months, and j
a.- At least once per 24 months, and                                     j
-b.
                    -b. Prior to returning the valve to service following maintenance, repair or replacement work on the valve which could affect its leakage rate.
Prior to returning the valve to service following maintenance, repair or replacement work on the valve which could affect its leakage rate.
The provisions of -Specification 4.0.4 are not applicable- for entry into     1 OPERATIONAL CONDITION 3.
The provisions of -Specification 4.0.4 are not applicable-for entry into 1
OPERATIONAL CONDITION 3.
4.4.3.2.3 The high/ low pressure interface valve leakage pressure monitors shall be demonstrated OPERABLE with alarm setpoints per Table 3.4.3.2-2 by performance of a:
4.4.3.2.3 The high/ low pressure interface valve leakage pressure monitors shall be demonstrated OPERABLE with alarm setpoints per Table 3.4.3.2-2 by performance of a:
: a. CHANNEL FUNCTIONAL TEST at least once per 31 days, and
a.
: b. CHANNEL CALIBRATION at least once per 18 months.
CHANNEL FUNCTIONAL TEST at least once per 31 days, and b.
FERMI - UNIT 2                     3/4 4-11a               Amendment No. pp,
CHANNEL CALIBRATION at least once per 18 months.
_                                                                                        J}}
FERMI - UNIT 2 3/4 4-11a Amendment No. pp, J}}

Latest revision as of 07:20, 10 December 2024

Proposed Tech Specs 4.4.3.2.2.a,changing Surveillance Interval in TS 4.4.3.2.2.a by Extending It from Current 18 Month Testing Interval to 24 Month Testing Interval to Be Consistent W/Asme Code Requirements
ML20199H250
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 01/28/1998
From:
DETROIT EDISON CO.
To:
Shared Package
ML20199G301 List:
References
NUDOCS 9802040451
Download: ML20199H250 (5)


Text

_ _ _..

Encl' sure 3 o

4

.NRC-98-0006 Page1 ENCLOSURE 3 FERMI 2 NRC DOCKET NO. 50-341 OPERATING LICENSE NPF-43 Rri UEST TO REVISE TECIINICAL SPECIFICATIONS:

TECIINICAL SPECIFICATION Cll ANGE Attached is a mark-up of the existing Technical Specifications (TSs), indicating the proposed changes, (Part 1) and a typed version of the TSs incorporating the proposed changes with a list ofincluded pages (Part 2).

9002040451 900128 PDR ADOCK 05000341 P

PDR

NRC-98-0006 Page 2 5

g ENCLOSURE 3-PART1 PROPOSED TECIINICAL SPECIFICATION PAGE MARK-UP

.J

E/JCl uiO C' &.5 N 2 0.- 4 7- 00 6 7 PR 6. G-7.-h eel.ll56 REACTOR COOLANT SYSTEM 24

~

SURVEILL ANCE REOUIREMENTS (Continuer" l

4.4.3.2.2 Each reactor coolant syst' ressure isolation valve specified in Table 3.4.3.2-1 shall be demonstrat PERABLE by leak testing pursuant to Specification 4.0.5 and verifying e leakage of each valve to be within the specified limit:

a.

At least once pe -16 months, and b.

Prior to returning the valve to service following maintenance, repair or replacement work on the valve which could affect its leakage rate..

The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 3.

4.4.3.2.3 The high/ low pressure interface valve leakage pressure monitors shall be demonstrated OPERABLE with alarm setpoints per Table 3.4.3.2-2 by performance of a:

a.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and b.

CHANNEL CAllBRATION at least oate per 18 months.

FERMI - UNIT 2 3/4 4-11a Amendment No.89

. NRC 98-0006 Page 3 ENCLOSURE 3-PART2 PROPOSED TECIINICAL SPECIFICATION REVISED PAGES c

3/4 4-11a

-u

-4

  • REACTOR COOLANT SYSTEM SURVEILLANCE RE001REMENTS fContinued) 4.4.3.2.2 Each reactor coolant system pressure isolation valve spheified in Table 3.4.3.2-1 shall be demonstrated OPERABLE by leak testing = pursuant to-Specification 4.0.5 and verifying the leakage of each valve to be within-the specified limit:

a.-

At least once per 24 months, and j

-b.

Prior to returning the valve to service following maintenance, repair or replacement work on the valve which could affect its leakage rate.

The provisions of -Specification 4.0.4 are not applicable-for entry into 1

OPERATIONAL CONDITION 3.

4.4.3.2.3 The high/ low pressure interface valve leakage pressure monitors shall be demonstrated OPERABLE with alarm setpoints per Table 3.4.3.2-2 by performance of a:

a.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and b.

CHANNEL CALIBRATION at least once per 18 months.

FERMI - UNIT 2 3/4 4-11a Amendment No. pp, J