ML18054B534

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Proposed Tech Specs Deleting Assignment of Functional Responsibility for Industry Operating Experience Review Program
ML18054B534
Person / Time
Site: Palisades Entergy icon.png
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 '; i I

TABLE 3.6.1 CONTAINMENT PENETRATIONS AND VALVES SYSTEM NAME AND VALVE PEN NUMBER SERVICE LINE SIZE ID NO REMARKS 39 CONTAINMENT HEATING CV-1503 Auto isolation valve; SYSTEM (4") Blind flange in required closure place during time = 25 seconds power operation 40 PRI-COOLANT SYSTEM CV-1910 Auto isolation valve; SAMPLE LINE (1/2") CV-1911 required closure time = 25 seconds 40A H MONITOR SV-2414A Auto isolation valve; 2

SV-2414B required closure (1/2")

time = 25 seconds 40B H MONITOR SV-2412A Auto isolation valve; I 2

SV-2412B required closure (1/2")

time = 25 seconds 41 DEGASIFIER PUMP CV-1004 Auto isolation valve; DISCHARGE (3") CK-CRW407 required closure time = 25 seconds 42 DEMINERALIZED CV-0155 Auto isolation valve; WATER TO QUENCH CK-V0155B required closure TANK (2") time = 25 seconds 44 CONTROLLED BLEED-OFF CV-2083 Auto isolation valve; FROM RCP'S CV-2099 required closure (3/4") time = 25 seconds 46 CONTAINMENT VENT CV-1101 Auto isolation valve; HEADER (4") cv-1102 required closure*

time = 25 seconds 3-40d Amendment No. tt~,

TSP0390-0305-NL04

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. 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 Amendment No. tll, TSP0390-0305-NL04

ADMINISTRATIVE CONTROLS e

6.5.2.6 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.

6.5.3 PLANT SAFETY AND LICENSING 6.5.3.1 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.

6.5.3.2 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.

6.5.3.3 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

ADMINISTRATIVE CONTROLS e

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.

6.10.2 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

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

.<.~~if

.... .* :*:.*" \."~i TABLE 3.6.1 CONTAINMENT PENETRATIONS AND VALVES SYSTEM NAME AND VALVE PEN NUMBER SERVICE LINE SIZE ID NO ~

39 CON'L\DOOUa'HEaING CV-1503 Auto isolation valve; SYSIEH (4'~)._ *: ... Bl tnd flange in required closure place during time

  • 25 seconds power operation 40 PRI-CX>OLAN'.r SYSTEM CV-1910 Auto isolation valve; SAMPLE LINE (1/2")
  • CV-1911 required closure time
  • 25 seconds 40A H2 MONITOR SV-2414A Auto f.solation valve; (1/211 ) SV-24148 required closure time c 25 seconds 408 n 2 MONITOR ci-&~~~j' Auto isolation valve; (1/2") . SV-24128 required closure time
  • 25 seconds 41 DEGASinER PUMP CV-1004 Auto isolation valve; DISCHARGE (311 ) CK-CRW407 required closure time c 25 seconds 42 DEHINERALIZED CV-0155 Auto isolation valve; WATER TO QUENcH CK-V0155B required closure TANK (2") time a 25 seconds 44 CONTROLLED BLEED-OFF. CV-2083 Auto isolation valve; FR<>>! RCP'S CV-2099* required closure (3/4") time
  • 25 seconds 46 CONTAINMENT VENT cv-1101 Auto isolation valve; HEADER (4") .CV-1102 required closure time
  • 25 seconds 3-40d *:.',._..,.:Ii)

Amendment No. /.i£,

September S, 1989 .*

,*j 06.89-0136-NL04 I,, *' ', ,_, ........ ~ .: .................. ..:' . . , ., >,~,,J~

3.25 ALTERNATE SHUTDOWN SYSTEM LIMITING CONDITION FOR OPERATION J

  • 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 ~ I

. 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

  • l provide equivalent shutdown capability and restore the inoperable .. l 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. jj.}J *

.Kay 19, 1989 TSP U85-0335-NL04

~

6.5.2.6 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 *..

Y.

~

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.

6.5.3. *PLANT SAFETY AND LICENSING * . c:J?

6.5~3.1 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 .

4 I

in design or operation to identify issues significant 'to I nuclear

. safety and recommend .nuclear. .safety_improvements~ .

6.5.3.2 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'utp1et 'E, 1989 1~8, I//;.

//.

TSP0189-0001-NL04

l ..

  • ADMINISTRATIVE. CONTROL.

e.

RECORD RETENTION (Contd)

~/~~ecords of changes made to the procedures* required by

  • '~'%'Specification 6. 8. L

- ---~;*' .

f."'"' Records of radioactive shipments.

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

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

6.10.2 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 PR ,lff:~=!'.!,~J-S~~~~~~t>y;~s~P

~I"-~~

1*-'f~,~-~~:~,

TSP0687-0001-NL04 *

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