L-87-238, Forwards Revised Pages to Inservice Test Program for Valves. Changes Required Due to Plant Changes/Mods or to Correct Errors in Inservice Test Program

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Forwards Revised Pages to Inservice Test Program for Valves. Changes Required Due to Plant Changes/Mods or to Correct Errors in Inservice Test Program
ML17347A527
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 06/05/1987
From: Woody C
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
L-87-238, NUDOCS 8706100107
Download: ML17347A527 (11)
v • d • e


Text

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FAC IL:50-250 50-251 AUTH. NANE WOODY> C. O.

RECIP. MANE REGULATORY I ORNATION DISTRIBUTION SYST (R IDS) 870b100107 DOC. DATE: 87/Ob/05 NOTARIZED:

NO DOCKET 0 Turkey Point P lant>

Unit 3> Florida Pouter and Lig h+

C 05000250 Turkey Point Plant>

Unit 4> Florida Power and Light C

05000251 AUTHOR AFFILIATION Florida Potoer 5 Light Co.

RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUB JECT:

Fortoards revisions to inservice

+est program For valves.

Changes required due to plan+ changes/mods or to correct errors in inservice test program.

DISTRIBUTION CODE:

A047D COPIES RECEIVED: LTR ENCL SI ZE:

TITLE:

OR Submittal:

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P. O. B 4000, JUNO BEACH, FL 3340B ziV lie arri n8 FLORIDAPOWER & LIGHTCOMPANY JuNF L-87-238 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:

Re:

Turkey Point Unit Nos. 3 & 4 Docket Nos. 50-250 and 50-25 I Revisions to the Inservice Test Pro ram - Valves Attached are revised pages to the Turkey Point Unit Nos. 3 & 4 Inservice Test (IST) Program - Valves.

Revisions are indicated by a single vertical line in the right margin.

These changes are required because of plant changes/modifications or to correct errors in the IST Program.

Revisions to the IST Program include:

I)

Pa e Nos. 29 and IOIA The existing 2-inch, high-head safety injection system test line return to the refueling water storage tank, air-operated globe valve Nos.'V-+-856A and CV-+-856B9 are being replaced by 2-inch motor-operated globe valve Nos.

MOV-+-856A and MOV-+-856B. Installation of these valves will be completed on Unit No. 3 by the end of the current refueling outage.

They are scheduled to be installed on Unit No. 4 during the next refueling outage.

2)

~acae 39 The existing 3-inch, steam supply to turbine-driven auxiliary feedwater (AFW) pump Nos. A, B, & C, motor-operated gate valve Nos. MOV-+-l4039 MOV-+-

l404, and MOV-+-l4059 are being replaced by 4-inch motor-operated globe valve Nos. MOV-+-l403, MOV-+-I404, and MOV-+-I405. Installation of these valves will be completed on both Unit Nos. 3 & 4 by the end of the current Unit No. 3 refueling outage.

3)

Payee 39 The existing 3-inch, steam supply to turbine-driven AFW pump Nos. A, B, and C,

stop-check valve Nos.

+- I 0- I I 9,

+- I 0-2 I 9, and

+-10-3 I 9, are being replaced by 3-inch tilting-disk check valve Nos. +-IO-3759+-IO-3769 and+-IO-377.

Installation of these valves will be, completed on both Unit Nos. 3 & 4 by the end of the current Unit No. 3 refueling outage.

8706100107 870605 PDR ADOCN 05000250 p

PDR TCG5/03 I / I PEOPLE... SERVING PEOPLE

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U. S. Nuclear Regulatory Commission L-87-238 Page two 4)

~Pa e 39 The existing 4-inch, steam supply to turbine-driven AFW pump Nos. A, B, and C, stop-check valve Nos. +-IO-I20, +-IO-2209 and+-IO-320 are being replaced by 4-inch tilting-disc check valve Nos. +-I0-3819 +-l0-3829 and +-l0-383.

Installation of these valves will be completed on both Unit Nos. 3 & 4 by the end of the current Unit No. 3 refueling outage.

5)

~acae40 The existing main steam isolation valve (MSIV) Nos. POV-+-26049 POV-+-

260S, and POV-+-2606, are check valves installed in the reverse direction.

Accordingly, these valves are classified as CODE category C (IWV-2200) valves.

In Table I, the failure mode of these Code category C valves was

listed, in error, as fail-closed (FC) because the MSIV actuator-spring was assumed to be a fail-closed spring.

We have now determined the actuator-spring is a partial-travel spring which only assists MSIV closure.

If there are any questions, please call us.

Very truly yours,

@ C. O. Woody Group Vice President Nuclear Energy COW/TCG/gp Attachment cc:

Dr. J. Nelson Grace, Regional Administrator, Region II, USNRC Mr. D. R. Brewer, USNRC Senior Resident Inspector, Turkey Point Plant Mr. D. G. McDonald, PAD2, USNRC TCG5/03 I /2

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FLORIDA POWER

& LIGHT COMPANY TABLE I TESTS TO CODE OR RELIEF REQUEST FAIL-REM.

VALVE CODE CODE ACT/

NORM.

URE POS ~

TEST ISI RRB VALVE NUMBER SIZE TYPE ACTU.

CL CAT..

PAS POS.

MODE IND ~

PER TESTS NO.

COORD REMARKS MOV-~-866A 2

GLOBE MO FAI 2

EP-2 6

2 EST-3 1

EP-5 D-15 MOV-*-866B 2

GLOBE MO B

FAI YES 2

EF-2 6

D-15 2

EST-3 1

EP-5

  • -876A
  • -876B
  • -876C
  • -876D
  • -876E 8

8 CHECK S/A 1

CHECK S/A 1

8, CHECK S/A 1

8 CHECK S/A

1 CHECK SfA 1

NC NC NC NC NC NO NO NO NO NO 2

EF-2 7

2 EP-2 7

B"15 A-13 2

EP-2 8

2 EP-2 8

A-13 A-11 2

EP-2 7

A-ll

  • -945E 1

S/CHK S/A AC NO NO 2

1 EP-2 SLT-1 5

C-9 MOV-*-856A 2

MOV-*-856B 2

GLOBE MO GLOBE MO 2

B NO NO PAI PAI YES 1

,1 1

YES 1

1 1

EP-3 "EST-3 EP-5 EP-3 EST-3 EP-5 21 D-3 21 D-3 SYSTEM TITLE:

SAFETY INJECTION SYS (SIS)

PROGRAM TITLE:

VALVE TEST PROGRAM

-,29-DWG. NO.:

5610-M-470-5

TURKEY POINT UNIT NOS.

3 6 4 RELIEF REQUEST BASIS SYSTEM:

Sa fe ty Injection 21.

Valve:

MOV-*-856A and MOV-*-856B Category:

B Class:

2 Function:

Isolation valves for the High-Head Safety Injection System Test line return to the Refueling Water Storage Tank

( RWST).

Test Requirement:

IWV-3410 Basis f or Relief:

Failure of either of these valves in the non-open position, by testing during either dual unit operation or single unit operation, would result in the isolation of the minimum recirculation flow path flow path from at least two High-Head Safety Injection pumps.

The isolation of the minimum recirculation flow path, concurrent with a Safety Injection Signal and high pressure in the reactor coolant

system, would result in damage to the associated High-Head Safety Injection pumps.

Alternate Testing:

These valves will be tested during refueling shutdowns of the associated unit when the High-Head Safety Injection pumps are aligned to the RWST of the operating unit.

-1 OOA-

FLORIDA POWER f LIGHT COMPANY TABLE I - TESTS TO CODE OR RELIEF REQUEST PAIL-REM.

VALVB CODE CODE ACT/

NORM.

URE POS.

TEST ISI VALVE NUMBER SIZE TYPE ACTU CL.

CAT PAS POS.

MODE IND.

PER TESTS COORD REMARKS MOV-*-1403 4

GLOBE 2

B NC FAI 3

EP-1 3

EST-3 1

EF-5

'-12 MOV-*-1404 4

GLOBE MO NC PAI 3

EP-1 D-12, 3

EST-3 1

EP-5 MOV-*-1405

,4

  • -10-083 4
  • -10-085 4
  • -10-087

. 4

  • -10-375 3
  • -10-376 3
  • -10-377 3
  • -10-381 4
  • -10-382 4

~ *-10.-383-4 AFSS-*-005 4

AFSS-*-0038 4

AFSS-*-003A 4

AFSS-*-003C 4

GLOBE MO CHECK S/A CHECK S/A CHECK CHECK S/A CHECK S/A 3

CHECK S/A 3

CHECK S/A 3

CHECK S/A.

3 CHECK S/A 3

CHECK S/A 3

CHECK S/A

~

3 CHECK S/A 3

CHECK S/A 3

B C

A A

NC NC NC NC PAI YES NO NO NO 3

EP-1 3

EST-3 1

EP-5 3

EP-1 3

EF-4 3

EP-1 3

EP-1 3

EP-1 3

BP-1 3

EP-1 3

BP-1 3

EP-1 EF-1 EF-1 I

EF-4 D-12 B-12 B-12 TRAIN 2 P-12 C-12 D-12 D-12 C-12 D-12 D-12 C-12 D-12 D-12 TRAIN 2 D-12 TRAIN 2 SYSTEM TITLE:

STEAM SYSTEM PROGRAM TITLE:

VALVE TEST PROGRAM DWG. NO.t 5610-M-1

t

FLORIDA POWER 6 LIGHT COMPANY TABLE I - TESTS TO CODE OR RELIEF REQUEST VALVE NUMBER CODE SIZE TYPE ACTU.

CL, CODE CAT FAIL-REM.

ACT/

NORM URE POS.

TEST ISI RRB VALVE PAS POS MODE IND PER TESTS NO COORD REMARKS POV-*-2604 26 POWER A/0 ASST'D CHECK C

A NO YES 2

EF-2

1 B-9 2

EST-1 1

EF-5

\\

POV-*-2605 26 POV-*-2606 26 POWER ASS'TD CHECK POWER ASST'D CHECK A/0 A/0 NO NO YES YES 2

EF-2 1

2 EST-1 1

EF-5 2

EF-2 1

2 EST-1 1

EF-5 B-10 B-ll

  • -10-004
  • -10-005
  • -10-006 26 S/CHK S/A 26 S/CHK S/A 26 S/CHK S/A NO NO NO NO NP 2

B-9 B-10 B-ll SYSTEM TITLE; STEAM SYSTEM PROGRAM TITLE>

VALVE TEST PROGRAM 40

DWG, NO. t 5610 "M-1
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