ML18057A507

Proposed Tech Specs Re Containment Penetrations & Valves, Making Editorial Changes

ML18057A507
Person / Time
Site:	Palisades
Issue date:	09/27/1990
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18057A506	List: ML18057A505 ML18057A507
References
NUDOCS 9010090009
Download: ML18057A507 (16)

Text

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ATTACHMENT 1 Consumers Power Company Palisades Plant Docket 50-255 EDITORIAL CORRECTIONS PROPOSED TECHNICAL SPECIFICATION PAGE CHANGES SEPTEMBER 1990, REVISION 1 ORIGINAL SUBMITTAL - 4/2/90 7 Pages*

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OC0890-0066-NL04

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I PDR ADOCK 05000255 I 1 P PDC

TABLE 3.6.1 CONTAINMENT PENETRATIONS AND VALVES SYSTEM NAME AND VALVE PEN NUMBER SERVICE LINE SIZE ID NO RE~.

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 (1/211 ) CV-1911 required closure time = 25 seconds 40A H2 MONITOR SV-2414A Auto isolation valve; (1/2") SV-2414B required closure time = 25 seconds 40B H2 MONITOR SV-2412A Auto isolation valve; I (1/2") SV-2412B required closure 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. t1S, TSP0890-0066-NLd4

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TABLE 3.6.1 OJNl'AilMN1' PENEIRATIONS AND VALVES SYSTEM NAME AND VALVE PEN NUMBER SERVICE LINE SIZE mm REMARKS 47 PRJMARY SYSTEM CV-1002 Auto isolation valve; DRAIN TANK PUMP CV-1007 required closure SUCTION (4) t:lme = 25 seconds 49 CLEAN WASTE CV-1038 Auto isolation valve; RECEIVER TANK CV-1036 required closure time = 25 seconds CIRCUI.ATION PUMP SUCTION (6") I e 52 CXJNTAm1ENI' SlMP CV-1103 Auto isolation valve; DRAIN W DIRIY WASTE CV-1104 required closure TANK (4")

• J time = 25 seconds 55 S (E"'.'"50B) SURFACE CV--0738 Auto isolation valve;

~(2) required closure t:ime = 25 seconds 67 CLEAN WASTE CV-1037 Auto isolation valve:

RECEIVER TANK PIMP CK-cRW400 required closure RECIRC ( 3") time = 25 seconds 68 AIR SUPPLY W CV-1813 Auto isolation valve; AIR RCXM (12") CV-1814 required closure time = 25 seconds 69 CLEAN WASTE CV-1045 Auto isolation valve; RECEIVER TANK PIMP CV-1044 required closure SUCTION (4") time = 25 seconds 3-40e Anendment No. tis TSP0890-0066-NL0.4

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3.25 ALTERNATE -SHUTDOWN SYSTEM

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LIMITING CONDITION -FOR OP-ERATTON 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 Eauipment" in Table 3.25.1 Operable, restore the inoperable eauipment to Operable within 7 days, or provide eauivalent shutdown capability and restore the inoperable eauipment 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.

Basts 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. tii, TSP0890-0066-NL04

ADMINISTRATIVE CONTROLS 6.5.1.4 MEETING FREQUENCY The PRC shall meet at least once per calendar month with special meetings as required.

6.5.1.5 QUORUM A quorum of the PRC shall consist of the Chairman and four members (including alternates).

6.5.1.6 RESPONSIBILITIES The PRC shall be responsible for nuclear safety review of:

a. All procedures and programs specified by Specification 6.8 and changes thereto, and any other procedures or changes thereto as determined by the Plant General Manager to affect nuclear safety; all proposed tests or experiments that affect nuclear safety; all proposed changes or modifications to plant systems or equipment that affect nuclear safety; and the Site Emergency Plan.

b. All proposed changes to Operating License and Technical Specifications.

c. Results of investigations of all violations of the Technical Specifications. (A report shall be prepared covering evaluation and recommendations to prevent recurrence and be forwarded to the Vice President - NOD and Nuclear Safety Service Department (NSSD).)

d. Plant operations to detect potential safety hazards.

e. Reports of special reviews and investigations as requested by the Plant General Manager or NSSD.

f. All reportable events as defined in Section 1.4.

g. All items identified under Specification 6.5.3.4 as significant to nuclear safety.

h. Monthly reports from Plant Safety and Licensing.

i. Nuclear industry operating experience. I PRC review of the above items may be performed by routing, subject to the requirements of Specification 6.5.1.7. PRC may delegate review of item a. to Plant Safety and Licensing as described in Specification 6.5.3 6-5a Amendment No. t~~. tl7, TSP0890-0066-NL04

ADMINISTRATIVE CONTROLS 6.5.1.7 AUTHORITY The PRC shall

a. Recommend in writing to the Plant General Manager approval or disapproval of items considered under Specifications 6.5.1.6.a. through i. above. I

b. Render determinations in writing with regard to whether or not each item considered under Specifications 6.5.1.6.a, b, c and g above constitutes an vnreviewed safety question.

c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President - Nuclear Operations and to the Nuclear Safety Services Department of any disagreements between the PRC and the Plant General Manager; however, the Plant General Manager shall have responsibility for the resolution of such disagreements pursuant to Specification 6.1.1 above.

The PRC Chairman may recommend to the Plant General Manager approval of those items identified in Specification 6.5.1.6 above based on a routing review provided the following conditions are met: (1) at least five PRC members including the Chairman and no more than 2 alternates, shall review the item, concur with determination as to whether or not the item constitutes an unreviewed safety question, and provide written comments on the item; (2) all comments shall be resolved to the satisfaction of the reviewers providing the comments; and (3) if the PRC Chairman determines that the comments are significant, the item (including comments and resolutions) shall be recirculated to all reviewers for additional comments.

The it~m shall be reviewed at a PRC meeting in the event bhat:

(1) comments are not resolved; or (2) the Plant General Manager overrides the recommendations of the PRC; or (3) a proposed change to the Technical Specifications involves a safety limit, a limiting safety system setting or a limiting condition for operation; or (4) the item was reportable to the NRC.

6.5.1.8 RECORDS The PRC shall maintain written minutes of each PRC meeting and shall provide copies to the NSSD.

6-6 Amendment No. l~. 7$, S$, s~.

l0S, ll7 TSP0890-0066-NL04

ADMINISTRATIVE CONTROLS 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 P-LANT- SAFETY- -AND* -LICENSING 6.5.3.1 FUNCTION The Plant Safety and Licensing organization shall function to examine proposed changes in design or operation and such other I matters as the PRC may assign to identify issues significant to I nuclear safety and reconnnend nuclear safety improvements.

6.5.3.2 COMPOSITION The Plant Safety and Licensing staff shall be composed of at least five experienced technic.al 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 eauipment.

d. The Site Emergency Plan.

6-9 Amendment No. 7$, $$, 1~$, 127, TSP0890-0066-NL04

,, :ADMINISTRATIVE CONTROLS RECORD- -RET-ENTION (Contd)

e. Records of changes made to the procedures reouired 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 eouipment 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 liouid 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 reouired by the QA Program Description.

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

i. Records of meetings of the PRC arid reviews performed by NSSD. I

j. Records of monthly facility radiation and contamination surveys.

6-27 Amendment No. 1$, 0t~¢t,

~it¢~ 1011a1g0, ~9. 10s, TSP0890-0066-NL04

I' ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255

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'EDITORIAL CORRECTIONS MARKED UP TECHNICAL SPECIFICATION PAGES SEPTEMBER 1990, REVISION 1 ORIGINAL SUBMITTAL 4/2/90

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7 Pages OC0890-0066-NL04

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• * *I TABLE 3.6.1 COH'.rAINMEN'J' PEHEl'RATIONS AND VALVES SYSTDt HAHE AHD VALVE PEN NUMBER SERVICE LIHE SIZE ID NO 39 CV-1503 Auto isolation valve; Blind flange in required closure place during time

• 25 seconds power operation 40 PRI-CX>OLAKr SYS'IEM CV-1910 Auto isolation valve; SAMPLE LIHE (1/2") CV-1911 required closure tiae

• 25 seconds 40A "2 HOtfll'OR SV-2414A Auto isolation valve; (1/2") SV-2414B required closure time

• 25 seconds 40B H2 tEN l1'0R . Auto isolation valve; (1/2") required closure time

• 25 seconds 41 DEGASIFIER PUMP CV-1004 Auto isolation valve; DISCHARGE (311 ) CIC-CRW407 required closure time

• 25 seconds 42 DEHIHERALIZED CV-0155 Auto isolation valve; WATER TO QUENCH CIC-V0155B required closure rANK (2 11 ) time

• 25 seconds CON'fROLLED BLEED-OFF CV-2083 Auto isolation valve; FRC>>I RCP'S CV-2099 required closure (3/4") tille

• 25 seconds 46 cotl'IAUIHEN't VENT cv-1101 Auto isolation valve9 HEADER ( 4 11 ) cv-1102 required closure time

• 25 seconds 3-40d .....

Amendment No. I.ii, September ~.--1984}-

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06.89-0l36-NL04 .. ,. *" a Wt,~ ._

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• TABLE 3.6.1 CONIAINMEN'r PENETRATIONS AND VALVES SYSTEM NAME AND VALVE PEN NUMBER ~VI~. ~!NE. SIZE IDN9 RF.MARKS 47 PRIMARY SYSTEM cv-1002 Auto isolation valve; DRAIN TANK P11MP CV-1007 required closure sucn<lf (4") . time

• 25 seconds 49 CLEAN*WASD CV-1038 Auto isolation*vaive; RECEIVER ?ANK CV-1036 required closure CIRCULArIOH PllMP time

• 25 seconds I SUCrIOM ~')

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S2 CONIAIIOOlla SUMP CV-1103

• Auto isolation valve; DRAIN to DIRTY WASD CV-1104 required closure rAHK (4") time

• 25 seconds SS S/G (E-SOB) SURFACE CV-0738 Auto isolation valve; BLOWDOW (2 11 ) required closure time

• 2S seconds 67 CLEAN WASD CV-1037 Auto isolation valve; RECEIVER ?ANK P11MP .CK-cRW408 required closure RECIRC (311 ) time

• 25 seconds 68 AIR SUPPLY to cv-1813 Auto isolation valve; AIR ROClt (12") CV-1814 required closure time

• 25 seconds 69 CLEAN WASD CV-lOltS Auto isolation valve; RECEIVER ?ANK PUMP CV-1044 required closure sucnoH (4") time

• 2S seconds 3"'.40e Amendment No. ~

~r , r,.l'm TSP0689-0136-NL04

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• 3.25 ALTERNATE SHUTDOWN SYSTEM

• LIMITING CONDITION FOR. OPERATION *- ,

3.25.l Tlie Alternate Shutdown System instrumentation and components shown in Table 3.25.1 shall be OPERABLE. Operability shall be demonstrated~e forming the surveillances in accordance with Section ~

i* ;).j 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 A.l.ternate 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

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with Regulatory Guide 1.97 and Appendix R to lOCFRSO.

3-134 Amendment No. j~j.J

. , . 19. 1989 TSP1185-0335-NL04

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. .fh-;, PRC':' sliall meet at. least once per cdendar month with *.~ .; * - -

.. ' .

- "~~~ecial_ meetings as. required~ _

. 6. 5

• L 5 ' QUORiiM: . .'

A quorum of: the PRC shall consist: of the Chairman and four members (including* alternates). * " _

RESPONSIBILITIES The PRC shall be responsible.for nuclear safety review of:

a *. All procedures.alid.progr~s specified by-Specification 6.8 I l

l

• and

• changes ther~to ;, and any other procedures or changes thereto as determined by the Plant General*Manager to* i affect nuclear safety; all proposed tests or experiments that affect nuclear safety; all proposed changes or

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modifications to plant systems or equipment that affect nuclear safety; and the Site Emergency Plan.

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b. All proposed changes to Operating License and.Technical Specifications.

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c. Results of investigations of ali violations of the Technical Specifications. (A report shall be prepared covering evaluation and recommendations to prevent recurrence* and be forwarded to the Vice President ~ NOD and Nuclear Safety Service Department (NSSD).)

d. Plant operations to detect potential safety.hazards.

e. Reports of special reviews and investigations as requested

• • by the Plant General Manager or NSSD.

f. All reportable events as defined in_ Section 1.4.

g. All items identified under Specifica.tion 6.5.3.4 as significant to nuclear safety.;

h *. Monthly reports from Plant Safety and Licens~ng.

. . . .

PRC review of the above items may be performed by routing, subject to the requirements of Specification 6.5.1. 7 *. PRC may delegate review of item a. to.Plant Safety and -Licensi~g as described in Specification 6.5.3

• I 6-5a Amendment_ No. t~8, ~

August 16, .1989 TSPO 1°89-000 l-NL04

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ADMINISTRATIVE CONTROLS 6.5.1.7 AUTHORITY The PRC shall:

a. *Recommend in writing Plant General Manager approval or di~approval of i ms considered under Specifications

6. 5. 1. 6. a. through 'Jt. above. I

b. Render determinations in writing with regard to whether or not each item considered under Specifications 6.5.1.6.a, b, c and g above constitutes an unreviewed safety question.

c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President - Nuclear Operations and to the Nuclear Safety Services Department of any disagreements between the PRC and the Plant General Manager; however, the Plant General Manager shall have responsibility for the resolution of such disagreements pursuant to Specification 6.1.1 above.

The PRC Chairman may recommend to the Plant General Manager f approval of those items identified in Specification 6.5.1.6 ~

above based on a routing review provided the following conditions are met: (1) at least five PRC members including the Chairman and no more than 2 alternates, shall review- the item, concur with determination as to whether or not the item ,_--

constitutes an unreviewed safety question, and provide written comments on the item; (2) all comments shall be resolved to the satisfaction of the reviewers providing the comments; and (3) if the PRC Chairman determines that the comments are significant, the item (including comments and resolutions) shall be recirculated to all reviewers for additional comments.

The item shall be reviewed at a PRC meeting in the event that:

(1) comments are not resolved; or (2) the Plant General Manager overrides the recommendations of the PRC; or (3) a proposed change to the Technical Specifications involves a safety limit, a limiting safety system setting or a limiting condition for operation; or (4) the item was reportable to the NRC.

6.5.1.8 RECORDS The PRC shall maintain written minutes of each PRC meeting and shall provide copies to the NSSD.

6-6 Amendment No. ii, 7J, SJ, Sf, t0S,~

-AtigasE lfi, 198U---=

TSPO 189.-000 l-NL04

ADMINISTRATIVE CONTROLS 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 CU\ ot~~r Ma.. tkrs c.c.S +h!. PRC m1.4y u ~~.-b~

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.

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 RE*SPONS IB UITIES 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 TSP0189-0001-NL04

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.. . . AD~ISTllATIVE

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- CONTRO-1/

RECORD RETENTION (Contd)

.... :. 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 CFB. 50.59. ~ -*

,.t;,. '-:iAc* *'~-;it, :J s pec.kr M d b7 tV 55 D. /

i. Records of meetings of the PR~~ __ . / ~

j. Records of monthly facility radiation and contamination surveys.

6-27

• • t** z01i11te, ,,,

Amendment No.

- October M, l987r ZJ, 0t4et, JP~)

TSP0687-0001-NL04