ML20116J936
| ML20116J936 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/31/1977 |
| From: | Ferrarello S GILBERT/COMMONWEALTH, INC. (FORMERLY GILBERT ASSOCIAT |
| To: | |
| Shared Package | |
| ML20116J740 | List: |
| References | |
| NUDOCS 9608140151 | |
| Download: ML20116J936 (35) | |
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m> Gilbert / Commonwealth en;; nee, and nnsuunu DO NOT REMOVE i
l G;LEERT ASSOC:ATES. !NC.. P. O. E:x MSB. Reacmg. PA 15503,Tel. 215 775-2500/Cacte GJas:c/Te!ex 5:5431 j June 7, 1977 1
FPC NO. 14415 (
Mr. R. S. Burns, H-8 CR-3 Engineering Manager Florida Power Corporation P. O. Box 14042 St. Petersburg, Florida 33733 Re: Crystal River Unit No. 3 Main Steam and Feedwater i Steam Hammer Observations !
and Instrumentation
Dear Mr. Burns:
Attached please find two (2) copies of a report entitled " Main Steam and Feedwater - Steam Hammer Observations and Instrumen-(~') tation". This document presents a fairly detailed history on l l
CJ the subject. l I
Should there be any questions, please contact me.
l Very truly yours, ;
SF: lap l Attachment g jj Santo Ferrarello i Piping Engineer !
cc: R. S. Burns, w/ attachment (2)
A. L. Gomez R. C. Bonner G. P. Beatty, Jr.
E. Morea w/ attachment E. R. Hottenstein, 2L F. J. Tomazic, w/ attachment M. Z. Lee, w/ attachment J. B'. Muldoon, w/ attachment A. P. Rochino, w/ attachment sept. 0430 File, w/ attachment G
5 5 tancas.ar Avese Sendmg PA B00 mal A.enue mom'ss.ng. FA / Morgantown Acad Green mus. :cacing PA 2?$ 775 25:0 C3 East Aasnm;'.an Avenue Jaason Mi 517 758 3000 / BD pee iveet New vara NY 212 422-3177
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FLORIDA POWER CORPORATION
] CRYSTAL RIVER NUCLEAR POWER PLANT 1
UNIT NO. 3 1
1 I
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1 MAIN STEAM AND FEEDWATER - STEAM HAMMER OBSERVATIONS AND INSTRUMENTATION l
l l
i 1
MAY 31,1977 ,
S. F. FmARELO l PIPING ENGINEERING DEPARTMENT GILBERT ASSOCIATES. INC. l i
. . - - - . - . . . - .. . - . . - . . . . . . ~ - . - . . - . . - . . - - . . - _ - . - . . _ - . _ _ . . . . -
I i
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! TABLE OF CONTENTS
)
j 1.0 Introduction Page 1 f 2.0 Steam Hammer Observation Page 2 !
3.0 Steam Hanumer Instrumentation Page 5 4.0 Conclusions Page 13 5.0 Recaimmendations Page 14 6.0 References Page 15 l'
. 7.0 Attacluments Page A-0 Attaciument 1 - Memo-S. Ferrare11o to F. J. Tomazic - Page A-1 Steam Hausner Observations (12/2/76)
- Letter from FPC to GAI Attaclument 2 - Memo-S. Ferrara11o to R..S. Burns / Page A-5 J. C. Hobbs - Skipping 15% Trip O Attactsnent 3 - Memo-il. Ferrara11o to F. J. Tomazic Page A-7 40% Trip Report Attactsnent 4 - Memo-S. Ferrara11o to F. J. Tomazie Page A-9 75% Trip Report Attacisment 5 - Calculation for Pressure Wave Propa- Page A-11 gation Speed Attachment 6 - Calculation for Dynamic Load Factor Page A-13 O 1 i
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1.0 INTRODUCTION
4 The final phase of design for a piping support system is observa- j i
tion during functional testing and during Initial Operation. For the l
main stesa and feedwater systems one of the most severe loadings oc-
]
curs immediately af ter the closure of the valves on the main steam j l
turbine chest. These particular valves are designed to close in a l
very short time in order to terminate the flow of steam into the Tur- l i
bine as quickly as possible. The abrupt termination of steam flow results in the creation of a pressure wave which travels from the Tur- ;
I bine steam chest, through the four scain steam lines, back towards the l l
Steam Generator. This wave is generated and dissipated before the i main steam bypass valves to the condenser or the safety valves to the atmosphere can open. The unbalanced force, normally referred to as a steam hammer, created by the pressure wave traveling through the pipe tends to accelerate the piping. Large restraints, primarily hydraulic I snubbers, were designed to arrest this unbalanced force.
In addition to visual observation by qualified GAI personnel, the main steam lines were instrumented to detect, and record, the pressure.
transient created. The recorded wave was then compared with the as-sumed curve used in the original steam hammer analysis.
The feedwater systemmight experience some water hammer as a result of the Turbine' Trips. Thus this piping was observed along with the main steam lines during the 40%, 75% and 100% Turbine Trips.
l 1
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4
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} 2.0 STEAM HANMER PIPING OBSERVATIONS i Section 5.4.4 of the CR3 FSAR (Pg. 5-64a and Pg. 5-64b) expresses i
F a commitment to ANSI B31.7, Paragraph 1-701.5.4, " Piping shall be i
^
arranged and supported so that vibration will be minimized. The
{
- designer shall be responsible by design and by observation under l -
i start-up and initial operating conditions to assure that vibration of piping systems is within acceptable levels".
Determining whether any given vibration is within " acceptable j levels" was made the responsibility of qualified personnel from GAI.
J Some written guidelines and specific piping areas to be observed l were included in a report, issued on 9/2/75, entitled, " Genera,1 i l j Acceptance Criteria for Dynamic Movement, Vibration and Thermal Ex-pansion of Piping for Crystal River Unit No. 3 Nuclear Plant". Test
! Procedures TP-600-14 and TP-800-25, in addition to providing checks
{ on pipe supports and rupture restraints, also include specific de-l tails necessary to translate the FSAR commitments into the realities.
}
For the piping systems in general, the FSAR commitment was fulfilled i
j_ by observations during Hot Functional Testing (July,1976) and Power i
- Escalation (March in April, 1977) by GAI Piping Engineer (s).
l
! The observations of the dynamic movement of the main steam and l feedwater lines, due to steam hammer, originally were planned only for the 24" $ main steam piping during the previously scheduled Tur-
{ bine Trips at the 15%, 40%, and 100% Power Levels. Later a Turbine l 1
Trip at the 75% Power Level was suggested by GAI (2ee Attachment 1).
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1
- In addition, one recommendation of the water hammer investigation of the j feedwater system (Reference 7) was to include this piping in the observa-i tion program during the intentional Turbine Trips, i During the early stage of the Power Escalation Program, FPC decided a
l not to do the 15% intentional Turbine Trip. GAI did not agree with this j i
l course of action (see Attac1snent 2). The first observation made for this l .
! steam hammer loading was at the 40% Power Level Reactor-Turbine Trip. Prior l to that test the GAI Engineer investigated a cut sleeve reported by the t
,! operations personnel. This sleeve surrounds the discharge stack for safety i valve, MSV33F, as it passes through the roof and is intended to anchor the l stack to the roof of the intermediate building. The cut was a 360 circum-i l ferential, found approximately three feet above the rooftop elevation. It was not the result of previous safety valve discharges. It appeared to be j made intentionally some time ago as evidenced by the overlap of paint, used on the exposed sleeve area, into the cut area. No reason for the cut was i aver determined. The cut sleeve was welded together immediately upon GAI's i
j reccamnandation.
] On 3/9/77 at 1510 hours0.0175 days <br />0.419 hours <br />0.0025 weeks <br />5.74555e-4 months <br />, personnel stationed in the Turbine and Inter-j mediate Building observed the Turbine Trip at the 40% Power Level. GAI's report on this trip is included in this report as Attachment 3.
}
1 4 The 75% trip was performed on 3/30/77 at 0830. GAI's report on this
{
. 1
( observation is included as Attachment 4. The grout used for steam hammer l'
- restraints MSH-227, 232, 236, and 240 was found to be deteriorating. GAI i
requested that the grout be removed (see Attachment 4). Upon further in-vestigation it was GAI's opinion that two of the concrete pedestals (MSH-
- O a 227 and 232) required revisions. New baseplates were designed (see Reference l 1 !
a
I O 13). Twelve holes were core-drilled into the Intermediate Building floor (el. 119'0"). Bolts were placed in the holes and an epoxy grout was used to bond the bolts to the floors (4/11/77). The snubbers were shifted from the pedestals to the new plates and welded on Saturday, 4/16/77 from 0100 to 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />. The 100% trip occurred on 4/18/77 at 1055. The Dynamic i
Movement, due to the travel of the pressure wave of the main steam lines (especially the two lines on the "B" loop) were significant but within values expected, and thus acceptable. The feedwater piping showed no ap-preciable movements.
The plant experienced an unintentional, and thus unobserved, trip at i
100% Power late on 4/18/77. MSE 227 and 232, as well as the other steam i i
hammer restraints, were checked, as they had been after the intentional trip, and were found to be free of any sign of damage or overloading.
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- 3.0 STEAM EAHMER INSTRUMENTATION l
i The steam hammer restraints were designed based on the best avail- l able pressure wave data at that time (1973). The Main Steam; Steam i I
Hameer Report for Crystal River Unit No. 3 (Reference 6) generated ;
l
! by M. Z. Lee (of GAI) on 11/2/73 contains the assumed curve as well i
j as the calculatio'sn for the loadings on each steam hammer restraint. '
i
! References "9a" to "9d" provides the history of the correspondence 4
between FPC and GAI on this subject. i Figure 1 is a schematic diagram of the instrumentation and its con- i i
- nection, through tubing, to the 24 inch diameter main steast lines.
Obtaining this data was included within Test Procedure TP-7-1-800-0,
" Power Escalation". The applicable sections are:
Section 6.5 Page 8
! 6.6 8 9.3.4 43, 43a, 43b Enclosure 16 i Part A 85 Part B 86 i
i Part C 87 i The data was recorded during the 40%, 75%, and 100% Power Level Turbine Trips (see Figures 2, 3, and 4). Please note that the pressure scale is different for the 40% test than that shown for the 75% and i
100% tests.
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- 4. The maximum slope of each curve has been determined and recorded. [
The slope used in the original design is 1280 psi /sec. It is this slope, along with the net pressure increase, and the speed of the propagation of the pressure wave that determines the unbalanced load-ing within the piping and 1Narted on the steam hammer restraints. i Table 1 presents these param'aters and determines this unbalanced force. i In addition, it provides a comparison with the numbers used in the )
initial design.
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O O O r
TABLE 1 (1) (2) (3) (4) (5) (6) (7) (8). (9) (10) (11)
STEAM WAVE PIPE WAVE MAXIMUM PIPE NET ACTUAL ORIGINAL RESTRAINT LINE HAMtER SPEED SEGMENT TRAVEL PRESSURE FLOW UNBALANCED LOADING DESIGN CAPACITY RESTRAINT USED LENGTH TIME RISE FORCE LOAD (milli-sec.) AREg)
(in (kips)
(ft/sec) (ft) (psi) (Fu) (kips) (kips) col.(4)/ Col.(6) x Col.(8) x Col.(3) Col.(7) D.L.F.
East Line MSH I from 238 1623 67.25 41.4 52 382 19.9 kip 22.9 28.8 49.5 S.C. "A" II Wzat Line MSH kip from 234 1623 85.25 52.5 96 382 36.7 42.2 36.6 49.5 S.G. "A" III East Line MSH kip .
from 232 1623 81.06 49.9 96 382 36.7 42.2 34.5 49.5 S.G. "B" IV West Line MSH P from 227 1710 98.6 57.7 96 382 36.7 42.2 42.3 49.5 S.G. "B"
. _. _ . . . _ _. _ . __ __ _ . _ _ _ .-_ _ _-- . _ ~ . - -__ _
e 2
'(V !
l j The wave speed (column 3) calculation appears in Attachment 5.
Lines II and III are assumed to have the same wave velocity as Line i I (conservative).
l 4 The pipe segment length (column 4) is that straight portion of 1
l piping which is restrained by the steam ham er restraint listed in column "2".
I
- The maximum pressure rise (column 6) is that =mr4=um pressure ;
increase that can be experienced within the wave travel time (column "5") anywhere on Figure 4.
The Dynamic Load Factor (DLF) used in column 9 is 1.15. Attach- )
{ ment 6 presents the calculations which arrived at that number. The l j original Design Load (column 10) includes a DLF of 1.5.
The not result is that the steam hammer restraint system as orig-l inally designed is sufficient to perform its intended function with-
]
1 out any modifications.
i.
i i ,
1 4
4
}
4 i n i
4
.)
i
O
4.0 CONCLUSION
S 4.1 Item 3 of Attachment 1 (page 2) states that the snubber failures found during _ot Functional Testing, all on Line III, was due to a water slug. Section 3.0 demonstrates the f act that the piping is sufficiently restrained for a 100% steam hamer force. There-fore, an increased credence must be placed on the water slug theory for the failures.
4.2 Observation of Feedwater System indicates that steam hammer in main steam lines does not create water hammer conditions within feedwster piping.
4.3 Steam hanumer instrumentation has served as a very valuable tool in determining the adequacy of the design and the actual margin of conservatism.
O
O 5.0 RECOMMENDATIONS 5.1 No steam hammer restraints be removed while plant is operating at a Power Level greater than 15%, without substituting a temp-orary restraint equal in capability to the original restraint.
i 5.2 Steam hammer restraints be observed on a periodic basis and im-mediately after each Turbine Trip from 75% load or greater for several more times to insure that no evidence of damage or un-usual wear occurs undected.
O O
l O
6.0 REFERENCES
l l
- 1) USAS B31.7-1969 Code for Nuclear Power Piping i
- 2) Crystal River Unit No. 3, " Final Safety Analysis Report", Sec- .
tion 5.4.4 Pages 5-64a and 5-64b. !
- 3) Test Procedure TP-7-1-800-0 " Power Escalation"
- 4) Test Procedure TP-7-1-600-14 " Supports & Rupture Restraint l
- Checks during Hot Functional Testing"
- 5) Test Procedure TP-7-2-800-25 " Supports & Rupture Restraint Checks during Power Escalation and at 100% Power"
- 6) Main Steam; Steam Hamner Report for Crystal River Unit No. 3 by M. Z. Lee, 11/2/73.
- 7) Feedwater Water Hammer Investigation for CR3 - by G. A. Delp l 10/11/76. ;
- 8) General Acceptance Criteria for' Dynamic Movement, Vibration 1
and Thermal Expansion for Crystal River Unit No. 3 Nuclear Power l Plant, by S. Ferrar 11o, 9/2/75. '
- 9) GAI - FPC Correspondence - Steam Hammer Measurements .
l a) 8/26/74 GAI to FPC, FPC No. 11321 b) 9/27/74 GAI to FPC, FPC No. 11549 c) 7/10/75 FPC to GAI d) 8/26/76 GAI to FPC, FPC No. 11321 l
- 10) Memo from S. Ferrara11o to F. J. Tomazie - 75% Trip Report, 4/7/77
- 11) Memo from S. Ferrar 11o to F. J. Tomazic - 40% Trip Report, 3/16/77
- 12) Memo from S. Ferrar 11o to R. S. Burns /J. C. Hobbs -
Skipping 15% Trip 2/1/77
- 13) Modification Approval Record #77-4-6A (70A) dated 4/7/77 O
_a 4 4 . ,p4 - .isn , .mcA.,.e _aa a.u.u A.Jg --.m.,,.J..a e. m ,..~._A.-A .+ - _ . . A.m-.A.._ _a4_#a.A.. _
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4 __ m e ***~~~ ~ . .~. ,, *w - m. ,o ,
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a 1
- 7.0 ATTACIMENTS 1
i I
1 1
i e
A-0
.~ ..
l I
ATTACW4G*3T ~
l A;/e, _
r 'h /, ;
g
- . =\ . :?ns Q
( jflb l Fkrida 'l i
P. o..w. .e. . .r.
December 20, 1976 g'f C.T.T.~ l ~
1 "h ~'*Z ; 101 w J l Mr. F.J. Tomazic Gilbert Associates, Inc. 3, EPT. 0430 i i P.O. Box 1498 Reading, PA 1 % 03
Subject:
Crystal River #3
- Observations of MS & FW Piping l 4
File: Main Steam Piping (
l l
Dear Mr. Tomazic:
4 l
i We have reviewed Mr. Ferrare11o's memo of December 2, 1976 on the
- O above subject (sent to us December 15) and have discussed this with j U Mr. J.D. Robison and Mr. S.F. Ferrare110.
t We concurr with GAI recemendations for piping observations during i the turbine trips, however, the steam hammer observations and measurements are R&D type work. Therefore, we authorize Mr. Robison and
- Mr. Ferrare11o as the qualified observers during the turbine trips. We l
would have no objections if GAI wishes to have other personnel j present during these tests at Crystal River #3.
4 R.S. Burns I cc: J. Alberdi G.P. Beatty
- J.C. Hobbs A.L. Gomes/J.E. Colby RSB/hw 1/12 O -7 14 w r' 6h 78-General Office 32o1 TNrty.courtn A-I str t soum . P O. Box 14o42. St I
~.'T , - . . -
! O memorandum Q oiise,eicommoo...ies
! I
. - December 2, 1976 i
- m
- F. J. TOMAZIC ,
from: S. F. Ferrare110 e 1,,
suWt: CRYSTAL RIVER UNIT NO. 3 - CBSUtVMION OF DYNAMIC RESPONSE
- r -
OF MAIN STEAM AND FEEDWATER SYSTEMS DURING TURBINE TPlPS i .
1 : 'd:. /
Test Procedure TP-800-0 calls for steam hammer measurements to be taken during Turbine Trips performed in the course of Power Escalation. The main steam and feedwater systems must
. R. , . be observed carefully, at that time, in order to determine-
- c .%'.- satisfactorily the response of the piping and support systems ,
O . ;;.. to dynamic conditions which result from turbine trips at sub- )
~-
i stantial power levels. This observation procedure has been i
_F,\ -- ~
employed, successfully, in the past by OAI to discover poten- ,
I J. tial dynamic problems in piping systems that have a tendency to resonate with forcing functions generated by turbine trips. l Discovery of these potential problems, at this stage, will en- )
hance the. reliability characteristic of the piping system'dur- i ing plant commerical operation. i
... The proposed plan for the Piping Engineering Department to ac-complish the above, is the following: l I) Prior to Power Escalation a) One person-visit to site to 40 Manhours ensure that instrumentation is installed properly.
II) During Power Escalation
' ' a) One person-visit to site 40 Manhours
- . at 154 power level to as-
~
sist in taking steam h~ammer measurements.
. b) Three person-visit to site 120 Manhours at 40% power level to ob-serve piping and supports.
O .
2
!O j
MEMORANDUM ATTENTION: F. J. TOMAZIC
. 1 l DECEMBER 2, 1976 l PAGE 2 B
- *c) Same as "b" except at 70% 4 120 Manhours Power '
s :.
l 6 d) Same as "b" except at 100% 120 Manhours Power
~ *
- Presently, FPC procedures do not call for a Turbine Trip be- )
tween that scheduled at the 40% and the 100% power level. In l
,. discussions, it was felt that GAI should recommend strongly, I to FPC, the addition of a Turbine Trip at some intermediate power level. The jump from the 40% to 100% power level was
., considered too large since the dynamic force generated by a
. ,- Turbine Trip varies with the square of the steam velocity and linearly with the pressure. Test Pr.ocedure TP-800-0 already has provisions for stopping at the 70% power level to perform
. .. certain tests. A Turbine Trip could be added conveniently at -
i this power level.
The four visits described in "a" to "d" perhaps could be reduced ,
.- to three if either no Turbine Trip is performed at the 70% power
. level or if more than one Turbine Trip can be covered in one ,
visit. An estimate of the total man-hours required are: )
11 person-visits x 40 man-hours = 440 man-hours
, person-visit l The considerations which resulted in the plan proposed above ares l (1) Since GAI, as the designer, has the taajor responsibility
- for the proper performance of the main steam piping and
.. supports, we should have our people on-site to evaluate their performance during the Turbine Trips.
(2) Although GAI strongly believes that a water slug was '
. the cause of the snubber failures on the one (of four) 3 main steam lines during HFT II, any uncertainty whie J. .still may exist can be further reduced by thorough (a.4
, , , servation of these lines (9/9/76 letter to FPC No.14021) .
(3) Since delays during Power Escalation can be especially costly due to delay of " Commercial Operation", peoplo L .. who can resolve quickly any problems discovered should be on-site during this period.
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ME!!ORANDUM ATTENTION: F. J. TOMAZIC DECEMBER 2, 1976 PAGE 3 i
(4) Feedwater Water Hammer Investigation Report (10/11/76) recommended observation of the Reedwater System simul-taneous with the main steazn syst'em during Turbine Trips. .
^~'
- If you have any questions or comments on the above, please ' call me.
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SANTO FERRARELLO
. SF: lap
'T, cc: E. R. Hottenstein ,
- J. B. Muldoon -
M. Z. Lee A. P. Rochino J. D. Robison O. .1 ,
Dept. 0430 File 4 .
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- AT7%C.M M 1 lA* h O 'nemorandum g eiise,,,c.mm ....i a A gg .,. , .,
February 1, 1977 to: R. S. Burns /J. C. Hobbs, Jr.
from: S. F. Ferrare11o subject: Observations of Piping during Power Escalation Turbine Trips e
Ic conversations Mth various testing personnel (1/30 and 1/31/77), it has come to my attention that Florida Power Corporation may adopt the following course of action:
- 1. Bypassing the 15% power testing including the intentional turbine trip.
- 2. Proceeding to 40% power testing.
. 3. Subsequent reduction in power; performance of loss of off-site ,
power test (unintentional turbine trip may result).
O4 I have discussed this matter with individuals in the Piping Engineering Department and the Project office. We disagree strongly, with this new
, course of action for the following reasonst
- a. Observations of main steam and feedwater lines can only be performed effectively with an " intentional" turbine trip.
- b. Proceeding to the 40% power level directly will almost certainly l result in inadvertent trips. These will not have been observed l
l and thus potential problem areas will not be identified.
1 c. The main steam turbine bypass valves are designed to accept a 15% power load rejection. The safety valves on the main steam should not lift during a 15% power turbine trip. Observations i
of the safety valves during such a trip will serve as a check on the load rejection system. The discharge piping from the dump valves require observations for excessive dynamic movements.
- d. Steam hammer measurements can only be taken during intentional turbine trips. The unfamiliarity of this test will result in missed data. The recording of this data at the 15% trip would provide experience on the part of the FPC technicians in obtain-ing this data. .
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- s. a R. S. Burns l Florida Power Corp.
j February 1, 1977 Page 2 j We, at GAI, share FPC's desire to bring CR-3 to the " Commercial Operation" 3
' r-date as soon as possible. However, accelerations of the Power Escalation
- Testing, as presently adopted, may result in the opposite effect. GAI i
recognizes its responsibility for the design of the piping systems. How-aver, proper escalation of power and observations of the piping are pre-requisites for the assumption of that responsibility. GAI cannot accept responsibility for the response of the piping systems which bave not been tested and observed in accordance with established procedures.
. be 5 j SFF:ejv S. F. Ferrare11o i
cc: E. R. Hottenstein (2) i F. J. Tomazic i B. F. Taylor i
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-..ies O memorandum g oiiaerezcomm March 16, 1977
- F. J. TOMAZIC I
I from: S. F. Ferrarello l
subrect: PIPORT OF VISIT TO CR3 SITE BY J. ROBISON AND S. FER-RARELLO FROM MARCH 7, 1977 TO MARCH 11, 1977 1
On Monday, March 7, 1977 it was lea that FPC (Operations-Testing) had advanced the schedule ower, Reactor-Turbine l Trip from March 11, 1977 to March 8, 1977. J. Robison and S.
Ferrarello departed that afternoon to fulfill GAI's responsi-bility of observing the piping and supports as authorized by R. S. Burns' letter of December 20, 1976. FPC. Operations -
Testing personnel reported, on Tuesday, March 8, that this 40%
trip might be cancelled. J. Robison and S. Ferrare11o briefly visited G. P. Beatty (FPC - Operations) to request that the m
test be performed as scheduled and to report GAI's position in i
this matter.
FPC argued that the two unintentioned trips experienced at the 40% power level was sufficient proof to the integrity of the piping and support systems. GAI stated that a fully observed i 40% trip was a necessary intermediate step in a proper and safe I escalation sequence especially since the 15% test was elimi-nated. The arrest of the tremendous energy generated during a trip by large snubbers supports and uncertaintities that cannot
.be factored into a design (e.g. installation) require that the last step in the design be the observation of the piping and supports at increasing energy levels from 0% to 100% power.
To FPC's credit, they did decide not to eliminate the 40% trip.
GAI did emphasize that a full Reactor-Turbine Trip was not re-quired for our purposes and that a Turbine Trip would suffice.
However, FPC had decided to re-instate the original Reactor-Turbine Trip as previously scheduled.
The reaction of the main steam and feedwater system was con-sidered satisfactory. The main steam lines evidenced the tre-mendous internal unbalanced forces, but the steam hammer re-straints kept the movement to within acceptable limits.
O
MEMORANDUM ATT ^" ION: F. J. TOMAZIC O FE.
PAGE e
', 1977 s
3 i
The instrumentation installed to record the steam hammer pulse worked well, the data has been recorded and is in
!i GAI's possession for. evaluation.
l !
At this writing, the 754' Turbine _ Trip is scheduled for March i 18, 1977. J. Robison and S. Ferrarello are planning to visit j the site to observe this test. Undoubtedly, FPC will be. con-
- templating the elimination of the 75% Trip. This is'certainly
}. ,
their prerogative but they should realize that we. object strongly for the reasons mentioned earlier.
}: A brief report on GAI's piping and support observations as well as a summary of the steam hammer, data collected will be sub-l 1- .
mitted to FPC after the 100% Tests are complete.
l FPC requested that S. Ferrarello stay one extra day to meet with FPC personnel working with the "2 inch and under seismic l support criteria". On Friday (March 11, 1977), I met with:
! i J. Colby j l .
D. Hodgson
- j. E. Morea i M. Tampa
{ Various questions were raised, discussed and answered.
e
,tjy SANTO FERRARELLO SF: lap cc: E. R. Hottenstein J. B. Muldoon I J. D. Robison Dept. 0430 File ,
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- l 73 RIEm0Pandum siibere/ common...ith t
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April 7, 1977 x F. J. TOMAZIC 5
from: S. F. Ferrarello subiect: REPORT OF VISIT TO CR3 SITE BY J. ROBISON AND S. FER-RARELLO FROM 3/20/77 TO 3/31/77 TO OBSERVE 75% POWER TURBINE TRIP on Sunday (3/20) it was discovered that thedEEP trip originally scheduled for Tuesday (3/22) had been postponed to Friday, (3/25).
However, it had been decided '. hat S. Ferrarello would depart as scheduled (3/20) and that J. Robison would follow at a date closer to the scheduled date for the 75% trip.
While on-site awaiting the trip, S. Ferrarello performed the fol-lowing tasks:
(1) Checked out steam hammer supports on periodic basis O (especially af ter two inadvertant turbine . trips) .
(2) Added restraints to reduce observed excessive vibra-tion (HDH-374 as well as two restraints for 1" di-amcter EX piping).
(3) Drew up As-Builts of "FS" piping discovered as a re-sult of resolving " hanger" vs. " piping" discrepancies.
(4) Assumed piping review duties for B. Seaholts for. Test Procedure 800-25.
Further delays resulted in scheduling the trip for 8:00 a.m. on Wednesday (3/30) . Jim Robison was present for the trip which was executed at 8:30 a.m. The piping reacted well to the steam hammer loading. However, the grout, for two of the steam hammer supports, which h:d been observed to be cracked prior to the test had deterioratOd even more. Upon review it was determined that, left as is, tne grout would fail completely and thus overload the bolts. FPC was requested to correct this situation (see attached memo).
The safety valve vent stack anchor found cut and corrected prior to the 40% turbine trip was observed to be holding up well.
4 9
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MEMORANDUM ATTENTION: F. J. TOMAZIC APRIL 7,1977 PAGE 2 l :
!- The steam hammer pulse data was obtained and is in GAI's pos-i session for review.
Only the 100% power level trip remains to be observed.
s 8y .= k fme4 L SANTO FERRARELLO SF: lap 1 cc: E. R. Hottenstein J. B. Muldoon J. D. Robison Dept. 0430 File l l i l l f l 1
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i I i l O h G ai'6 re'ca- - - '** 1 1 March 30, 1977 ) 2: J. Colby hsm: S. Ferrare11o i 1 l 2 ' subject: Steam Hammer Restraints MSH 227, 232, 236 and 240 The reaction of the piping and supports to the Turbine Trip performed this morning (75% Power Level) was quite satisfactory. i However the grout used for the subject steam hammer supports has d been deteriorating steadily this past week. Further disintegration
- of this grouting was anticipated with a result of the failure of l these supports to perform their intended function. Therefore I l recommended to Mr. G. P. Beatty, Jr. that
1
- 1. Grout be eliminated; steel plate would rest on concrete pedestal. l
() 2. Work be performed immediately.
- 3. Power level be reduced to approximately 15% until med-4 ifications were completed (6 hours estimated).
- Recommendation "3" was made since it was felt that the piping sys-l tem might not withstand a trip at a higher power level if these sup-i ports are not active.
As of this writing, 2:30 p.m. , FPC Operations has responded quickly 1 and is in the process of making these fixes. 4
-N
, Santo Ferrare11o j GAI Piping Engineer
- SF
- mak ze: F. J. Tomazic J. B. Muldoon
; J. D. Robison G. P. Beatty, Jr.
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