ML18054B534

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Proposed Tech Specs Deleting Assignment of Functional Responsibility for Industry Operating Experience Review Program
ML18054B534
Person / Time
Site: Palisades 
Issue date: 04/02/1990
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18054B533 List:
References
NUDOCS 9004110086
Download: ML18054B534 (10)
v • d • e


Text

ATTACHMENT 1 Consumers Power Company Palisades Plant Docket 50-255 PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES -

April 2, 1990 4 Pages TSP039Q-0305-NL04

/

9004110086 900402 PDR ADOCK 050002ffi5 P

PDC

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PEN NUMBER 39 40 40A 40B 41 42 44 46 SYSTEM NAME AND SERVICE LINE SIZE CONTAINMENT HEATING SYSTEM (4")

PRI-COOLANT SYSTEM SAMPLE LINE (1/2")

H2 MONITOR (1/2")

H MONITOR 2

(1/2")

DEGASIFIER PUMP DISCHARGE (3")

DEMINERALIZED WATER TO QUENCH TANK (2")

CONTROLLED BLEED-OFF FROM RCP'S (3/4")

CONTAINMENT VENT HEADER (4")

TSP0390-0305-NL04 TABLE 3.6.1 CONTAINMENT PENETRATIONS AND VALVES VALVE ID NO CV-1503 Blind flange in place during power operation CV-1910 CV-1911 SV-2414A SV-2414B SV-2412A SV-2412B CV-1004 CK-CRW407 CV-0155 CK-V0155B CV-2083 CV-2099 CV-1101 cv-1102 REMARKS Auto isolation valve; required closure time = 25 seconds Auto isolation valve; required closure time = 25 seconds Auto isolation valve; required closure time = 25 seconds Auto isolation valve; required closure time = 25 seconds Auto isolation valve; required closure time = 25 seconds Auto isolation valve; required closure time = 25 seconds Auto isolation valve; required closure time = 25 seconds Auto isolation valve; required closure*

time = 25 seconds 3-40d I

Amendment No.

tt~,

3.2S ALTERNATE SHUTDOWN SYSTEM LIMITING CONDITION FOR OPERATION 3.25.1 The Alternate Shutdown System instrumentation and components shown in Table 3.25.1 shall be OPERABLE.

Operability shall be demonstrated by performing the surveillances in accordance with Section 4.21.

APPLICABILITY:

Reactor coolant temperature ~ 325°F.

ACTION:

a.

With less than the "Minimum Equipment" in Table 3. 25.1 Operable, restore the inoperable equipment to Operable within 7 days, or provide equivalent shutdown capability and restore the inoperable equipment to Operable within 60 days; or be in Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Cold Shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

The provisions of Specification 3.0.3 and 3.0.4 do not apply.

Basis The operability of the Alternate Shutdown System ensures that any fire will not preclude achieving safe shutdown.

The Alternate Shutdown System components are independent of areas where a fire could damage systems normally used to shut down the reactor.

This capability is consistent with Regulatory Guide 1.97 and Appendix R to 10CFR50.

3-134 Amendment No. tll, TSP0390-0305-NL04 I

e ADMINISTRATIVE CONTROLS 6.5.2.6 6.5.3 6.5.3.1 6.5.3.2 6.5.3.3 RECORDS Records of NSSD activities shall be maintained.

Reports shall be prepared and distributed as indicated below:

a.

The results of reviews, performed pursuant to Section 6.5.2.4.1 and Section 6.5.2.4.2, shall be reported to the Vice President -

NOD at least monthly.

b.

A report assessing the overall nuclear safety performance of Palisades shall be provided to senior Consumers Power Company management annually.

PLANT SAFETY AND LICENSING FUNCTION The Plant Safety and Licensing organization shall function to examine proposed changes in desj_gn or operation and such other I

matters as the PRC may assign to identify issues significant to I

nuclear safety and recommend nuclear safety improvements.

COMPOSITION The Plant Safety and Licensing staff shall be composed of at least five experienced technical staff, reporting to the Plant Safety and Licensing Director, to carry out these functions.

RESPONSIBILITIES The Plant Safety and Licensing staff may provide nuclear safety review as delegated by PRC for:

a.

Procedures, programs and changes thereto identified in Specification 6.8 and any additional procedures and changes thereto identified by the Plant General Manager as significant to nuclear safety.

b.

All proposed tests or experiments.

c.

All proposed changes or modifications to plant systems or equipment.

d.

The Site Emergency Plan.

6-9 Amendment No. 7$, $$,

t~S, tl7, TSP0390-0305-NL04

e ADMINISTRATIVE CONTROLS 6.10.2 RECORD RETENTION (Contd)

e.

Records of changes made to the procedures required by Specification 6.8.1.

f.

Records of radioactive shipments.

g.

Records of sealed source leak tests and results.

h.

Records of annual physical inventory of all source material of record.

The following records shall be retained for the duration of the Facility Operating License:

a.

Record and drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.

b.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c.

Records of monthly radiation exposure for all individuals entering radiation control areas.

d.

Records of gaseous and liquid radioactive material released to the environs.

e.

Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.

f.

Records of inservice inspections performed pursuant to these Technical Specifications.

g.

Records of Quality Assurance activities required by the QA Program Description.

h.

Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

i. Records of meetings of the PRC and reviews performed by NSSD.

I

j. Records of monthly facility radiation and contamination surveys.

6-27 Amendment No. !$, 0t~'t,

~it'~ t01l<<IS0, ~9, t0S, TSP0390-0305-NL04

TSP0390-0305-NL04 ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 MARKED UP TECHNICAL SPECIFICATION PAGES April 2, 1990 4 Pages

SYSTEM NAME AND PEN NUMBER SERVICE LINE SIZE 39 CON'L\\DOOUa'HEaING SYSIEH (4'~)._ *:...

40 PRI-CX>OLAN'.r SYSTEM SAMPLE LINE (1/2")

  • 40A H2 MONITOR (1/211 )

408 n2 MONITOR (1/2").

41 DEGASinER PUMP DISCHARGE (311 )

42 DEHINERALIZED WATER TO QUENcH TANK (2")

44 CONTROLLED BLEED-OFF.

FR<>>! RCP'S (3/4")

46 CONTAINMENT VENT HEADER (4")

06.89-0136-NL04 TABLE 3.6.1 CONTAINMENT PENETRATIONS AND VALVES VALVE ID NO

~

CV-1503 Auto isolation valve; Bl tnd flange in required closure place during time

  • 25 seconds power operation CV-1910 Auto isolation valve; CV-1911 required closure time
  • 25 seconds SV-2414A Auto f.solation valve; SV-24148 required closure time c 25 seconds ci-&~~~j' Auto isolation valve; SV-24128 required closure time
  • 25 seconds CV-1004 Auto isolation valve; CK-CRW407 required closure time c 25 seconds CV-0155 Auto isolation valve; CK-V0155B required closure time a 25 seconds CV-2083 Auto isolation valve; CV-2099*

required closure time

  • 25 seconds cv-1101 Auto isolation valve;

.CV-1102 required closure time

  • 25 seconds 3-40d
  • .',._..,.:Ii)

I,,

~.:....................:'

Amendment No. /.i£,

September S, 1989

.<.~~if

. **:*:.*" \\."~i

,*j

....,,., >,~,,J~

3.25 ALTERNATE SHUTDOWN SYSTEM LIMITING CONDITION FOR OPERATION

  • ifl:.- -

3.25.1

  • T}i;e1:Alternate Shutdown System instrumentation and components show11 in Table 3. 25. 1 shall be OPERABLE.

Operability shall be demonstrated&ff>erforming the.surveillances in accordance with Section ~

11* ~I APPLICABILITY:

Reactor coolant temperature~ 325°F.

ACTION:

a.

With less than the Minimum Equipment" in Table 3. 25.1 Operable,,

restore the inoperable equipment to Operable within 7 days, or provide equivalent shutdown capability and restore the inoperable equipment to Operable within 60 days; or be-in. Hot Shutdown within.:.

the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Cold Shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.*

b.

The provisions of Specification 3.0.3 and 3.0.4 do not apply.

Basis The operability of the Alternate Shutdown System ensures that any fire will not preclude achieving safe shutdown.

The Alternate Shutdown System components are independent of areas where*a fire could damage systems normally used to shut down the reactor.

This capability is consistent with Regulatory Guide 1.97 and Appendix R to 10CFR50.

3-134 TSP U85-0335-NL04 Amendment No. jj.}J *

.Kay 19, 1989 J

I

  • l l

6.5.2.6 6.5.3.

6.5~3.1 6.5.3.2 RECORDS Records.of NSSD activi~iesshal.l be maintained.* -Reports shall

  • .' *. be prepared* and~ distributed*. as indicated below:
a.

The results of reviews, performed pursuant to Section 6.5.2.4.1 and Section 6.5.2.4.2, shall be reported *to the Vice President -

NOD at.least* monthly.

b.

A report assessing the overall nuclear safety performance of Palisades shall be provided to senior Consumers Power Company management annually.

  • PLANT SAFETY AND LICENSING FUNCTION

. t 1 J-.

Sut.k otk~r vwd.\\.er5 ct$ fflt!. PRC Mo..y a ~Si-~n*

The Plant Safety and icensing organization shall function to examine proposed changes.

in design or operation to identify issues significant 'to nuclear safety and recommend.nuclear safety_improvements~

  • COMPOSITION

\\

The Plant* Safety and Licensing_staff-~hali°be composed of at least five experienced technicai-.staff, reporting to-the Plant Safety and Lice1fsing Director, *to carry out these functions.

RESPONSIBILITIES

  • 1*

The Plant Safety an& Licensing staff may provide nuclear safety review as delegated by PRC for::

a *.. Proce.dures,. programs and. changes thereto identified in Specification 6.8 and any additional procedures and changes thereto identified by the Plant General Manager

.. as significant. to nuclear safety.

b. *. All proposed tests or.experiments.

c *.

All proposed changes ci'r modifications to plant systems or_ equipment. * *

d.

The Site Emergency Plan.

6-9

  • .. *"*,:** ~ -,

Amendment No. 7J*,- 8J, 1~8, I//;.

TSP0189-0001-NL04 1'utp1et 'E, 1989

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~*

4 I I

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Y...

  • .. ~

l ADMINISTRATIVE. CONTROL.

e..

6.10.2 RECORD RETENTION (Contd)

~/~~ecords of changes made

  • '~'%'Specification 6. 8. L

---~;*'

f."'"' Records of radioactive to the procedures* required by shipments.

g *. Records of sealed so.urce leak tests and resui'ts.

h.

Records of annual physical inventory of all source material of record.

The following records shall be retained for the duration of the Facility Operating License:

a.

Record and drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.

b.

'{!:

Records of new and irradiated fuel inventory, fuel transfers*,._ *

  • ~
c.
d.
e.
f.

and assembly burnup histories.

Records of monthly radiation exposure for all individuals entering radiation control areas.

Records of gaseous and liquid radioactive material released to the environs.

Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.

Records of inservice inspections performed pursuant to these Technical Specifications.

g.

Records of. Quality Assurance activities required by the QA Program Description.

h *.'* Records of reviews performed for changes made to procedures or

... equipment or reviews of tests and experiments pursuant to

-, -10 CFR 50.59.

!!=--*~~-:;:..;-.:....:;;._-.,;.;;--::.;:,.-~::--:~-------,.,,

i.-~ Records of meetings of the PR,lff:~=!'.!,~J-S~~~~~~t>y;~s~P1

  • -'f~,~-~ ~:~,

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TSP0687-0001-NL04 *

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