L-76-415, Forwards Preoperational Test Procedure No. 0700080B,, Steam Generator Feedwater Hammer Test.

Forwards Preoperational Test Procedure No. 0700080B,, Steam Generator Feedwater Hammer Test.

ML18127B127
Person / Time
Site:	Saint Lucie
Issue date:	12/07/1976
From:	Robert E. Uhrig Florida Power & Light Co
To:	Ziemann D Office of Nuclear Reactor Regulation
References
L-76-415 0700080B
Download: ML18127B127 (22)

Text

NRC FORM 195 pl U.s. NUCLEAR REGULATORY COMMISSION DOCKET NUMBER 12.7GI ~ i FILE NUMBER NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAl DATE OF DOCUMENT Mr Ziemann Florida Power & Light Co LL Miami, Fla Hhrig DATE RECEIVED R E ]2 ]e /6 HLETTE R IZIf4OTOB IZED f'ROP INPUT FORM NUMBER OF COPIFS RECEIVED S ORIGINAL RUNG LASS IF I E D one signed DCOPV DESCRIPTION ENCLOSURE Ltr trans the following: "Steam Generator Feedwater Hammer Test"......

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@ )ggy FLORIDA POWER & LIGHT COMPANY December 7, 1976 l L-76-415 Office of Nuclear Reactor Regula I 6 ~<<ufo Attn: Dennis L. Ziemann, Chief I1RC Operating Reactors Branc ' 'Qgpa Division o f Operating Re c r@QQ 1 O 3 S. Nuclear Regulatory Commiss'~ma<<~ ~~10'.

Washington, D.C. 20555

Dear Mr Ziemann:

Ch Re: St. Lucie Unit No. 1 Docket No. 50-335 Operating License DPR-67 Enclosure 1 Item C.l Enclosed'.herewith for your review is a copy of the St. Lucie Plant Unit No. 1 Preoperational Test Procedure No. 0700080B,"Steam Generator Feed-water Hammer Test," which we plan to perform to satisfy the subject license condition. This test procedure was informally given to members of your staff on November 19, 1976.

It is our understanding that members of your staff wish to witness the per-formance of this test. Florida Power 6 Light Company prefers to conduct this test following an unscheduled trip from greater than thirty percent of full rated power for the following reasons:

1) the remaining scheduled trips during the power ascension test pro-gram are not compatible with the conduct of this test,

2) a trip scheduled specifically to perform this test would cost Florida Power & Light Company customers approximately $ 58,000.

The NRC will be notified at least two days before the plant conditions are such that this test could be performed so that appropriate plans may be made for witnessing the test.

The final procedure as implemented may reflect minor revisions ma'de in accord-ance with St. Lucie Technical Specifications. Any such changes will not, how-ever, alter the intent of the test.

Our present schedule indicates that we could be ready to perform the attached test as early as December 14th, 1976. We, therefore, request any comments PEOPLE... SERVING PEOPLE

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To: Dennis L. Ziemann December 7, 1976 Re: St. Lucie Unit No. 2 Page Operating License DPR-67 which you may have on either the attached procedure or plans for its per-formance prior to December 12, 1976, so that any such comments might be factored into our plans.

Yours very truly, Robert E. Uhrig Vice President REU/ls Encl.

cc: Norman C. Moseley, Region II Robert Lowenstein, Esq.

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PREOPE~NAL TEST PROCEDURE No. 07000 STEAl~i GENERATOR FEEDHATER HA~Q'1ER TEST i Revision l 0

5.0 Instrumentation

The following parameters shall be monitored and/or recorded 'during the test. (S/G 1B level and Aux FWP flow to S/G 1B shall be con-tinuously recorded during steps 12.2 thru 12.3.

NOTE: Aux H~P flow will probably be pegged high at 300 gpm.

Aux H6'A & 1B Amperage (Record while feeding up)

Pzr Pressure ~ - S/G 1A & 1B Level Pzr Level S/G lA & 1B Pressure Loop 1A & lB Hot Leg Temp. Aux BG'low to,S/G 1B Loop 1A & 1B Cold Leg Temp. Aux H6'ressure:.

Loose Parts llonitor (if in service).

6.0 Related System Status:

6.1 Atmospheric steam dump and SBCS are operational.

Verified by Date 7.0 ecial Haterials or E ui ment: ) ' 2 S ~ I 7.1 Temporary recorders (as necessary) 8.0 Tem orar Connections:

'Pomnorarlr recorders'ay bq conrlpcted Section 5.0 in addition to installed recorders/indicators; --

~ Le 9.0 Precautions & Limits:

9.1 The test shall be aborted if S/G level is off scale. Recovery shall be made in accordance with EP 0700040, Loss of Feedwater or Steam Generator Level.

9.2 The test shall be aborted if RCS cooldown is excessive.. Co'oX-down shall not exceed 75F/hr. The test shall be aborted of Pzr level reaches 27%.

9.3 The fourth 'RCP shall be secured below 510F (Tcold).

9.4 The preferred mode of adding feedwater during the feedup test is via motor driven Aux H6'o minimize heat removal from the RCS.

9.5 If SBCS is used for temperature control during the hold period, I-HCV-08-IB shall be closed to minimize level decrease in S/G 1B The setpoint of I-HCV-08-2B shall be raised to 920 psig in auto.

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. 0 PREOPERATIONAL TEST PROCEDURE No. 07000808, STEA".1 GENERATOR FEED'HATER HAKER TEST

9. 0 (cont) 9.6 Only persons authorized by the Test Director and/or Nuclear Plant Supervisor are allowed in containment.

10.0 Acce tance Criteria:

10.1 The test is complete upon successful completion of steps 12.2 and 12.3 with no audible or visual indications of damagi>>

Feedwater hammer.

11.0 Records Re uired:

11.1 The completed copy of this procedure with applicable recorder traces shall be filed in accordance with QI 17-PR/PSL-l.

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• PREOPERA NAL TEST PROCEDURE- NO. 070008 Rev. 1 STER'I GENERATOR FEEDS'ATER 1bQL1ER TES

12. 0 Detailed Instructions:

12 ' Initi.al Setup & Steamdown 12.1.1Comm nce raising'Pressurizer level to at least 45%.

Charging pump high level override bypass may be used to allow running 2 charging. pumps i.f desired. Mhen level is at 45%, switch to Backup RRS. This step shall be completed by 12.3,4. Proceed with 12.1.2-12.3,3 12.1. 2 concurrently.

Verified by 'ate Transfer control of S/G 1B pressure 'from the SBCS

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to the atmospheric dump by placi.ng the I-HCV-08-2B controller setpoin't to the existing S/G pressure in auto and closing I-HCV-08-1B. Verify that the atmospheric dump opens and that pressure- is being controlled by it.

Time of trip . Pre-trip Power level Verified by Date 12.1.3 Raise the pressure setpoint for I-HCV-08-2A. to 920-

, psig. Raise the pressure setpoint on SBCS to 930 t

psia. Maintain water level in S/G lA by reducing e

feed flow.

Verified by a

Date n

12. 1;4 Reduce the level in S/G 1B by discontinuing feed to that generator and by maintaining its pressure at 900 psia.

Verified by Date 12.1 ~ 5 Note the time that S/G 1B level drops below 34 '% .

(Bottom of Beadvater Thermal Sleeves) .

Time Verified by Date

12. 1 e6 Note the time that S/G 1B level reaches 29%.

Time Verified by Date

12. 1.7 Verify Blowdown is secured from'S/G 1B.

Verified by Date 12.2 Hold Period (2 hrs. or 5% Level) 12.2 ~ 1 Vhen S/G 1B level has dropped to between 27% & 29%,

reduce the setpoint on SBCS to 900 ps%a and increase'

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PREOPERATIONAL TEST PROCEDURE NO. 0700080B, Rev. 1 STEQl GENERATOR FEED'HATER 1hQMER TEST 12.0 (cont) 12.2 (cont) 12.2.1 (cont) the setpoint for I-HCV-08-2B to 920 psig. Verify that steam flow from S/G 1B atmospheric dump has decreased.

Verified by Date I = 4 p 12.2.2 Feed S/G IA as necessary to maintain a level of 65%.to 70%. Verify the RCS .temperature is con-trolled by S/G IA.

Verified by Date 12.2.3 Near the end of the hold period, verify an observer is stationed in the area of the Aux FtG'nd that "

communications are established with the control room.

Verified by Date 12.2.4 Hear the end of the hold period, perform the following:

.All Pzr backup htrs ON P'I $ P2 Pzr heaters Q'hf Verify Pzr pressure controlling via Pzr spray. Pzr pressure setpoint may have to be adjusted .to maintain 2250 psia.

Verified by Date NOTE: If S/G IB level approaches 5%, immediately .

proceed to step 12.3.

12.3 Feedup Test a

12.3.1 'Verify that 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> have passed since the time recorded in step'12.1.5 ~or that S/G IB level is at 5%. Record the timt Verified by Date 12.3.2 Verify there has been no feedwater addition to S/G 18 during the above time interval.

Verified by Date 12.3.3 Secure Blowdown from S/G IA.

Verified by Date

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PREOPERATIONAL TEST PROCEDURE No, 07000808,

. ~ Rev. 1 STEAN GELlERATOR FEED'hATER HsQQ'ER TEST 12.0 (cont) 12.3 (cont) ft 12.3.4 Station an observer inside the personnel airlock with the inner door open a few inches to listen for PM hammer. Using two motor driven Aux HK's, iniate feedwater flow to S/G 1B in accordance with OP 0700022 (perform steps 8.2.2 and 8.2.5 concurrently.)

Establish as close to maximum flow (all valves in Aux H4 flow path. to S/G 1B open) as cooldown rates allow.

If cooldovn rates appear excessive, make small 're-ductions in Aux H6'lov.

I NOTE: Aux Pv header flov indication only goes to 300 gpm -use amperage to estimate flow. Since experience indicates cooldown rate will not be a problem, it is expected that we will have maximum flow from the two motor driven Aux FHP's.

Verified by Date

'ate 12;3.5 Increase level in S/G 1B to greater than43~ while maintaining feedvater flow at the above established Qbsel ¹>>s sh 1 3 eco d thci>> ob,e ticns QQ the su~mary sheet. Record lA & lB AKf pump amperage on summary sheet.

Verified by 12.4 System Restoration 12.4.1 Reduce feedwater flow to S/G 1B to desired amount to minimize RCS cooldovn. Mhen S/G 1B level is above .

50K, setpoints for SBCS and both atmospheric dump controllers (I-HCV-08-2A & I-HCV-08-2B) may be Reset to 'nornel no-load conditions. I-HCU-08-1B may be opened. 5faintain norrwl hot shutdown steam generator.

levels.

Verified by Date 12.4.2 Regain normal control of Pzr pressure.

Verified by 12.4.3 Initiate Blowdovn from S/G 1A, and S/G 1E.

Verified by Date 12.4.5 Collect all data, recording charts and document observations of personnel.

Verified by Date

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a 1) p PREOPER XONAL TEST PROCEDURE Yo. 07000, Rev. 1 STEPu~f GENERATOR PEED'HATER HA~a&ER TEST 13.0 Deviatioris:

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t Page 8 of 8 REVISION 1, PREOPERATIONAL TEST PROCEDURE HO, .07000SOB r

PREOPERATIONAL TEST SENARY REHARKS

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