Text

Rev 1 to RHR Team Rept
	ML20236E712
Person / Time
Site:	Pilgrim
Issue date:	05/05/1986
From:	; BOSTON EDISON CO.
To:	;
Shared Package
ML20236E691	List: BECO-86-062, Responds to NRC Confirmatory Action Ltr 86-10 for Restart of Plant Re 860404,11-12 Events at Plant; ML20236E712; ML20236E725;
References
	NUDOCS 8710290321
	Download: ML20236E712 (607)
	v • d • e

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h Dr. Thomas E. Murley Page 6 Finally, five analog (Non-0) signals will be used to monitor Reactor Pressure i and Reactor Water Level. The analog signals will be rear' by high quality, high input impedance amplifiers.and will not interfere with Control Room (

indication. One spare contact from the mode switch will be monitored to flag switch movement, plant personnel will be stationed at key locations (e.g.,

control room) to observe any abnorn'al or unusual conditions. This testing will include bringing the plant up to approximately 20 percent of rated power and allowing the plant to stabilize for approximately eight hours. An orderly l shutdown will be conducted and monitored with the GETARS. If the isolation event occurs during this shutdown, this system will capture it and an applicable corrective action plan will be developed. Barring an MSIV closure and Scram, a normal ascent to full power operation is scheduled. Monitoring of the PCIS system will continue until the installation of the EPIC computer system is completed, at which time the temporary monitoring system (GETARS) will be removed. The EPIC system project scope will be increased in accordance with our Long Term Planning process to include " monitoring" points similar to those selected to be monitored by GETARS. Those additional points 1 will allow us to more readily assess the root cause or initiating events for transients of the nature that we experienced in March and April,1986.

Conclusion The basis for re-start (from the RHR perspective) is partially based on recently conducted local leak rate testing on the RHR injection line which indicate rates averaging one-sixth (1/6) of the 10CFR50 Appendix J acceptance criteria. M0-1001-288 valve will be physically opened and inspected to determine the need for further work. The existing design features have been tested and found to perform as designed. These will be supplemented with modification to limit the potential for overpressurization of the low pressure portion of the RHR system through the use of a controlled leak-off path and ;

enhanced capability to monitor for intersystem leakage.

The basis for re-start (from the MSIV perspective) is that root cause has been established and recurrence of the MSIV pilot poppet disassociation has been precluded by repairs made. Additionally, MSIV leakage rates will be reported and evaluated under separate cover (LER).

The basis for re-start (from the perspective of the Mode Switch) is that testing performed to date indicates the only failure mode to be a spurious PCIS Group I isolation. It is possible that the root cause(s) for the spurious closure of the MSIV's will hcVe been corrected by replacement of the mode switch, the redressing of the water level instrument cables, or the repairing of the neutral connections on the PCIS relays. The controlled operational test under carefully monitored conditions will determine if the problem has been corrected or indicate the need for additional corrective action. Should the operational testing not cause a duplication of this event, ,

a normal increase to full power operation is scheduled to take place. '

[, Continued inproved methods of moriitoring shall serve as a means to analyze any future trah'sients of this kind.

8710290321M[h93 PDR ADOCK O PDC' l

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Or. Thomas E. Murley Page 7 He would ask, therefore, that you review the information enclosed at your earliest convenience and, if you concur, provide us approval to re-start PNPS.

If you require further information on these issues, please do not hesitate to l- contact us.

I Sincerely, t W. D. Harrington Attachments:

Attachment (1) RHR Team Report Attachment (2) MSIV Team Report Attachment (3) Mode Switch Team Report Attachment (4) BECo Dispositioning of RHR Team Recommendations Attachment (5) BECo Dispositioning of MSIV Switch Team Recommendations Attachment (6) BECo Dispositioning of Mode Switch Team Recommendations I

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ATTACHMENT (1)

RHR TEAM REPORT i

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'mBLE T CONTENTS

' RHR 'DE FOICE 'REPORP Ji. Report Sumary

11. RHR Task Force Menbers

'I. . Purpose II. Technical Description of Leakage Path III. - Description of E'mnt i

-IV. "ask Force Focus i

, V. Description of Problem

. VI. Inpact of Leakage VII. . History VIII. Investigation -

IX. Influence of RHR Ieakage on Other RHR System Pr&lems X. . Root Cause Analysis -

J XI. Recommendations .

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XII. Restart Analysis Appendix A - 1986 RHR Chronology Appendix B - Possible Sources of High Pressure Fluid Ieakage Into RHR Appendix C - Failure 4 Malfunction Reports (86-036,86-084, 86-085)

Apperdix D - RHR Task Force ESR's Issued Appendix E - OIC Meeting Minutes 86-16, Including SE 1918 Appendix F - RHR System Flow Recorder Information Part I - Determination of the Nur.ber of 'B' RHR Loop Pressurization Part II - FR1040-7 History l Part III - FR1040-7 Raw Data !

L I Appendix G - RHR Task Force Walkdowns l l

Appendix B - Hydrodynamic Test Results l Appendix I - Local Ieak Rate Test Results i

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BBLE & CONITNTSI(continued) -

Appendix J - Procedures used by RHR Task Force .;

~*Walkdown Plan

TP86 *'IP86-58

Procedure 8.7.1.5 r-. Appendix K - Listing of Documents Reviewed by RHR Task Force.

Appendix L - Local Ieak Rate History of.1001-29B-28B Apperdix M - PDC-86-20 Containing Cause Analysis of Head Spray Failure

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, 'JM 86-13 M01001-36 Valve Repair

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, Appendix N - RHR Motor Operated Valve Maintenance History-Appendix 0 - Check Valve 1001-68B Rebuild Records i.

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SLMAFY.

his report provides an analysis of the MIR system conditions which led to I the declaration of an unusual event and subsequent shutdown on April 11, 1986.

Pepeated annunciation of the "RHR Discharge or Shutdown Cooling. Suction High Pressure" alarm proupted speculation that MO-1001-28B and 29B were leaking.

Although appropriate operator action was taken, there was no method of accurately quantifying leakage through the system. n is led to the assunption that there was a failure of primary containment isolation valves (MO-1001-28 and 29 B) and a shutdown was initiated.

We Task Force was assenbled and "as fourd" walkdowns were performed. With this initial data, the team proceeded along two primary paths: one of further testing and analysis and the secord, gathering historical data.

We results of these investigations formed the basis for this report.

The Appendix J criteria for MO-1001-28B ard 29B is 7.89 SLM at 45 psig.

%ese valves were tested on April 18th with leakage rates of 1.5 and 1.0 (respectively). n ese tests show that there was not a failure of these primary containment isolation valves on April 11, 1986.

We have performed a problem analysis of this situation and provide two (2) alternatives for innediate (prior to startup) resolution.

A) Of corcern is the leakage past check valve 1001-68B and the

[. MO-1001-28B and 29B valves which was the cause of the MIF pressuri-U zation problerrs. We recomnerd at least one of these valves be dis-assenbled, inspected ard repaired (as necessary) .

OR B) The 68 valves have no leakage criteria (they are not primary con-tainment boundary) and the 28B and 29B valve leakage is well within 10CFR50 Apperdix J criteria. An alternative to Besolution A is to allow a controlled leakage path in the RHR system to mitigate system pressurization. Although the Task Force does not recotmend this approach, it is an alternative.

In eddition to the above, several further recco1merdations are presented no matter which approach is taken:

1. Perform a orce per Refueling Outage leak test on 1001-68A ard B

2. Install additional pressure gauges in the system

3. Develop a detailed system venting program

4. Provide a neans for system temperature nonitoring

5. Bevise the alarm procedure for edditional corrective action

RPtlAW (continued) -

Also, several long term recommendations have been made and are described in the body of this report. l i

It is the conclusion of this task force that given the uncertainties of the MIR system on April 11, the decision to declare an unusual event and connence shutdown was appropriate (especially in light of subsequent plant events). However, focusing mly on the RHR system (the initiating event),.

we have determined that the health and safety of station personnel and the general public was not jeopardized, and the shutdown would not have been required if additional system monitoring capabilities had been avail 21e to ,

. assess the leakage integrity of the containment isolation valves. j 9

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l RHR TASK FOFCE MEMEERS The RHR Task Force consisted of the following enployees. '!he dedication and involvement of the individual team menbers led to the expedient identifica-tion and quantification of this problem.

MEMBER NOINAL DEPAR'IMENT Patl Cafarella NED - FSOC David Heard NED - FS&MC Charles Martin RD - OSS&P Peter Manderino NCD - OSS&P Paul Cormier NID - Technical Richard Mattos NCD - OSS&P Andrew Felix ED - OSS&P .

Michael Maguire NCD - Maintenance Marie Lenhart VP - RA&P '-

Donald Phinney ED - Maintenance Dennis Kuba KD - OSS&P Jack Coughlin NED - PS -

1 Leo Judge NED - I&CS Stmley Wollman NCD - OSS&P i

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. RHR TASK FON:E REPORT 'Page 1 ~

I. PURPOSES

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' Si RHR hsk Force was assenbled to investigate the severity of the "B" Loop .i RRt system leakage which was the initiating event for the shutdown which be:Jan on April 11, 1986. Se RHR Task Force was chartere$ to seek root ca)se of the event, to determine its relationship to previous events, and to de termine if the leakage represented a challenge to safe operation of Pil-grim Station.

This report provides recommended actions to be taken: prior to restart, prior to cycle 8 startup, and long term.

II. 'ITHNICAL DESCRIPTION & UAKA2 PA'Im Se Residual Heat Removal system has two (A & B) injection paths for LPCI

. - and/or shutdown cooling. Fran just outside the containment boundary, valves are arranged in a series of M01001-28, an 18. inch globe valve; M01001-29, an- ;

18 inch gate valve and 1001-68, an 18 inch tilting disk check valve. Se injection path enters the 28 inch recirculation system piping at the discharge side of the punp. (See figure 1 for configuration and figures 2, 3 .

and 4 for valve outline drawing). - RHR system leakage on the 'B' Loop propa-gated across the 68B check valve through the 29B gate valve and (when closed

- on 4/11/86) the 28B globe valve. Se M01001-28B and 29B valves are contain-ment isolation valves (CIV's) per Technical Specifications. Se result of .

. this leakage was a slow pressurization of RHR piping outboard of the 28B 4 valve. We water leakage, as was seen by pressurization, inplied that the CIV's were not seating and may not have been within; allowable leakage rates.

Testing of CIV's is required by 10CFR50,. Appendix J and ~is performed with air tects at design' accident pressure and'is measured in volume per unit time.

Typical units used at PNPS are standard liters per minute (SLM) of air.-

Ris air leakage measurement is not typically equatable to water leakage, on a matherratical basis, as seen in pressurization events, but can be equated on a case by case basis only if the appropriate testing is done.

Se outboard RHR piping is nonitored by pressure switches PS-1001-74A, 74B and 82 which provide a conson alarm through annunciator B-7 on the left side of Panel C903 in the Control Room. 21s alarm alerts Operatior.s of an over-pressurization cordition. Operator action to correct this conSition is to .:

relieve pressure (normally) through M01001-34A and M01001-36A to the Torus (Procedure 2.3.2.1).

III. DfjgRIPTION T EVENT While starting up the plant on April 10, the RHR alarms on C903 were annun-l clating at frequent intervals (as often as every 15 minutes on the 8-4 i shif t) . Eis was the first indication of a problem in April 1986 (a similar event had occurred in January-February 1986). It was observed that applying more seating force to the 29B valve reduced the leakage rate as determined by alarm frequency. We decision was made to proceed to power operation and determine the severity of the situation from the frequency of alarm annunciation.

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RHR TASK FOICE REPOIE (continued) Page-2 DESCRIPTIOti T EVENT (continued) -l

'the torque switch for the Mol001-29B was incre.ased to a setting of 3 (up

' from 1.5) on AprilE10,1986. 'the' 'B' loop was in Torus . cooling until- 1200 .

hours-on 4/11. - At 1415 hours0.0164 days 0.393 hours 0.00234 weeks 5.384075e-4 months , the RHR system high pressure alarm was received and the first ICO for LPCI inop and containment-isolation valve failure was entered when M01001-28B was closed.in the line (reference Tech. ,

. Specs. 3.5.A.5 and 3.7.D.2 respectively) . Tech. Spec. 3.5.A.5 is a 7-day ICO. At 1653 hours0.0191 days 0.459 hours 0.00273 weeks 6.289665e-4 months , the RHR high pressure alarm annunciated .again with 2 i containment valves in series closed causing entry into Tech. Spec. 3.7.D.3, ;

a 24-hour ICO and an unusual event. It should be. notal that because leakaae ;

intD. Abg MR system yla the CIV's could DQi bg mmtifind. Abe. valves hgl 19. l be assumed 19. nQi magt 10CFR50 Appendix J. leakage critaria.

IV. - TASK FOICE FOCUS

' h task force focused in on the 'B' RHR Loop because: j i

A. If-PS1001-82 pressure switch (outboard the shutdown cooling line '!

Containment Isolation Valves) was the cause, letdown of pressure via !

M01001-34A & 36A would not relieve the pressure condition. Also, if leakage

occurred through the shutdown cooling path, the leakage would go to the Torus via the Mol001-7A-D valves rather than to the system because-static pressure is 6 psig in the Torus versus 100+ psig in the system.

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- b B. When the alarm on Panel C903 annunciated, in January 1986, the 29 - ,

-- # and 28 valves for both systens were walked down. W 28B valve was reported

" hot" . 'therefore, the conclusion was made that the leakage path was the 'B' RHR loop. +

An additional review of possible inleakage sources was corducted and is l contained in Appendix B of this report. 'Ihe results of the review also )

conclude that the 'B' loop injection path was the source of the 1 pressurization.

V. QL9CRIPTIQ4 & PRCELEN:

Severe leakage through containment isolation valves (CIV's) in the RHR system leads to two fundamental problems:

Problem 1; The RHR valves are suspect in their ability to provide contain- l ment isolaticn with respect to primary containment leakage.

Problem 2: Leakage from the high pressure reactor coolant system could lead I to overpressurization of the lower pressure rated RHR piping. At its worst, failure of the RHR system could result with a consequent loss of reactor water coolant inventory. Such a worse case condition is termed "an inter-system IOCA" or an " Event V of WASH 1400" occurrence.

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RHR TASK FOK2 REPORT (continued)1 Design features to prevent a worst case event of overpressurizing the_ low

.: pressure system aret A. - Valves M01001-2EB(A)' and M01001-25B(A) ^are interlocked;to prevent simultaneous opening of both valves in the line when reactor pressure is above 400 psig. '

q B. Pressure switch PS1001-74B(A) alerts the Operator to a' high pressure .

. condition due to high pressure leakage or loss of RHR flow path'. ,

1 C. Relief valve PSV1001-22B(A) 'is on the RER system outboard of M01001-28B and has been testad to lift at 428 psig and allow a flow of 54 gpm -

e (at' 500 psig) to mitigate overpressurization of low pressure rated piping.

D. Check valve 1001-68B(A) serves to limit the amount of leakage and

)

preserve vessel inventory until the M01001-28B(A) 'and/or 29B(A) valves go -

closed should there be a pipe break in the RHR system.'

VI. IMPACT T IZAKAGE Leakage past the M01001-28A(B) and 29A(B) valves has the potential to overpressurize the RHR system and overheat thus create steam voids in the

- RHR system.

Overpressurization of the RHR system was evaluated by the neasuring of O - high pressure fluid leakage. Se B' loop injection path had a measured outleakage of .33 gpm. his is not a viable concern because (1) Se system is designed for pressures in' excess of PSV-1001-22's relieving pressures '(428 psig), and (2) Se measured flow rate of 0.33

. gpm past the valve is well below the relieving capacity of the two 54 gpm PSV-1001-22 valves.

Ieakage could also cause ' overheating and voiding of the RHR system. If a lame steam bubble formed downstream of an isolation valve, it could 0 contribute to a water hamer during RHR punp startup. Ieakage of 500 F water into the RHR piping in large volumes could result in these local ,

corr 11tions, since the saturation temperature of water at 110 psig (keep fill pressure) is approximately 345 F.

Although it might be possible to raise the water temperature locally above 345 F and create a steam bubble, there is no evidence of severe water hamer in the vicinity of the 28 or 29 valves. We supports have been inspected and'show no sign that a water hammer event had occurred.

l During operation it was noted that the piping between the M01001-28B i and M01001-29B valves was " hot". " Hot" was interpreted as being a sur-face temperature of approxinetely 150 F. Cbserved leakage rates do not appear sufficient to cause formation of a steam void.

It should be nota 3 that there is evidence of vibration in the 'B' RHR line. A one-inch test connection between 33 and 68 valves suffered a fatigue failure at a sockolet weld and the pressure seal bolting on the 29B va] ve had two loose nuts.

i f

_____a-_:___ __ _ _ . - _ - _ _ - _ _ _ _

~ RHR TAEK FOICE REPORF (continued) . Page 4 1

IMPACT. T LEMGM . (oontinued) -

Because of the uncertainties of analytical methods of determining local temperatures in bulk systems, it is recommended that' local . temperatures, be monitored ard the system be vented periodically to determine if a .

prcblem exists.

.VII. . HIS'IURY Leakage past the closed M01001-29A and B valves occurred in the mid to late 70's. One corrective action taken was to change the valve lineup from M01001-29 A&B normally closed to normally open and M01001-28 A&B from normally open.to normally closed. l I

. Written operating records are' silent on the pressurization stbject until l January 26, 1986. At this time, the RHR pressurization alarms (Panel C903) 1 l were noted to occur at a regular frequency. 'Ihere were discussions con-L -cerning the problem but no action was taken. . On February 18, Failure and Malfunction Report (F&M)86-036 was issued ,to officially identify the , q problem. NED was consulted on the issue for advice in two areas -First, 1 could the leakage through M01001-28B be quantified by calculation? Second,

.could the valve alignment be changed to M01001-29B closed and 28B open? NED responded to the calculational question by saying that a correlation between . -l

' air (for Local Leak Rate 10CE'R50, Appendix J) and water were not defensible.

as this-correlation would have to be based on enperical data which was specific for the valves.in question. Appendix C of this report contains the

[

Failure & Malfunction Reports and the disposition of F & M 86-036.

NED responded to the valve alignment change with Safety Evaluation #1918 which permitted valve realignment. In fact, the "new" alignment'was in-accordance with original system design. Both of NED's responses were

' presented at OIC Meeting Nunber 86-16 held .on February 19 and are part of the meeting minutes. Olc Meeting 86-16 minutes 'are incorporated into this report as Appendix E.

Ihe valve alignment was changed as per Safety Evaluation (1918 and the pressurization problem was not evident for 16 days (until the Head Spray shutdown). Failure and Malfunction Report 86-036 was closed out regarding significance by an evaluation presented in Memo STA86-026 dated March 4, i 1986. J 1

1 4

. _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ________________________________.____.________________________.___._______________________.___..__.____J

l gl 4 L .

.. .. Page 5.

}!

RHR MSK F01CE REPORP'(continued) ~

u

]l HISmRC (continued)' d 1

(h33[gi]EE Pressurization Events:

Because there were questions about the initiation of the RHR pressurization problem, the Task Force performed'a review of plant logbooks. We Operating' )

>- Supervisor's logbook, the STA logbook and the Watch Ihgineer's logbook were j reviewed to determine when the RHR events occurred. Se logbooks were 'i reviewed and a composite chronology was made. : Sis chronology is Appendix A - )

of this report. Se first formal log entry was in the Sm logbook for? l January 26,1986. %ere are no other. notations of any abnormalities in the 1

.< RHR system prior to this date.

Verbal information obtained from,various plant staff members indicated that )

the RHR pressurization problem was present prior to January 1986.-1Sirce 1

written logbooks do not provide a positive' reference, another investigatory )

method was discovered. Se alternate method involves-a unique phenomena that is manifested in RHR flow recorder FR1040-7. When the RHR piping was pressurized, the B system flow pen on FR1040-7 responded, providing a .

-recorded; history of the RHR system. Appendix F of his report explains the connection between RHR pressurization events and the response of FR1040 ,

and presents the data collected from the charts for the 1985-1986 period. '

L he' record of RHR pressurization events is presented as Figure 5. . An examination of Figure 5 reveals, for the period of January 1985.through.

August 1985, that pressurization were infrequent, with only 27. days when

_ pressurization events occurred. %ere is some correlation between RRR pressurization events and reactor startups; there were 6 unit startups in the' January to July 1985 period. %ere were 4 RHR pressurization events on the:same day or day after unit startup.- This correlation may be due to the ;

use of Shutdown Cooling and/or Inservice Test Program Opening tests of 1001-68B.

In September 1985 there is a significant increase in the frequency of coeurrence as presented in Figure 5. Were are 15 pressurization events between September 9 and September 30 or a 70% occurrence rate. m is frequency increase occurred directly after the unit startup from the 'B' recirc punp seal outage on Septenber 7,1985. Se 'A' RHR system was used for shutdown cooling for this shutdown but Procedure 2.1.7.B was performed when shutdown cooling was terminated. Procedure 2.1.7.B requires the

-establishment of 4400 gpm for a short time through the RHR loop not used for shutdown cooling, in order to verify injection check valve 68B opening operability. Procedure 2.1.7.B is performed to meet the Inservice Test Program (IST) requir(ments of valve operability. Another significant finding from Figure 5 is that equipnent qualification modifications on RHR valve M01001-28B were begun on Septenber 13, 1985 - four days after the frequency of pressurization increase.

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Page 6 i L

o

- MIR TASK FOK2 REPORT (continued) ~

HIS'IORI (continued)'

Further examination of Figure 5 for the months of Octd>er 1985 through. .

' February 1986 shows that the frequency of pressurization remains high.- ne - l FR1040 chart for October 10 through Novenber 10 could not be located Lin i Document Control, so that a frequency similar to Septenber and Novenber is

j. - assumed.-

' VIII. INVESTIGATION

' A. Investigation Method 1

%e RHR Task Force-initiated investigation of the pressurization problem in l uultiple paths. ~ Specific procedures used by the.RHR. Task Force are

. contained -in Appendix J of this report.

a L

. %e paths were:

As found walkdown of the system to capture existing conditions and I configurations j i

Hydrodynamic test to determine actual high pressure system leakage ;)

through the 3 valves in series on the 'B' RHR loop -

fA

Hydrodynamic test to determine high pressure system leakage through J

-h the M01001-28A valve on the 'A' RHR loop

Air leakage test on check valve'1001-688, followed by Apperdix J tests ~

on valves HQ1001-29B and M01001-28B l i

Research of PNPS operating records, maintenance histories, Failure and Malfunction Reports, LER's and other documents to aid in a search for l root cause and interrelationships j

Collection of irdustry data from INPO, valve vendors and other utilities for input of technical infonnation and lessons leamed by f) others jl B. Walkdowns Walkdowns of 'B' Loop RHR were conducted to look for the effects of over-pressurization on system piping and couponents. S e latent effects of water hanmer, over temperature corditions, and leakage were the nain focus of the walkdown.

l

%ere were no significant findings; minor findings included a pipe support I that had a questionable design, loose pressure seal nuts on 29B and q f

indication of high temperatures between 28 and 29B. None of the findings l were indicative of a water hamner event. j l

J

__E___ ______m_ _ _ _ . . _

w a ']

L L: RHR TASK FOICE REPORT (continued)' Page 7 l'

L INVESTIGATION '(continued)

One notable 'walkdown observation is that little or no leakage exists on the

'B' RER system' outboard isolation valves. Se leak tightness of the system '

'is seen as a contributor to the' frequent high pressure alarms.

2 ere was evidence of water leakage at the hinge pins of the 1001-68B check valve, and the blanket ' insulation on it exhibited evidence of wetting. Scme but not al1 of the wetted' insulation is attributed to the 1-inch test -

L connection leak that was discovered in January 1986. Se water leakage may be indicative of vibration problems in the system or from wear on the hinge pin seals. Task Force walkdown results are contained in Appendix G of this p report.

C. Water Tests The high pressure. water (hydrodynamic) test was performed on the 'B' loop to j quantify _ the actual leakage at pressure. Se results of the 'B' loop water i tests weres ;

Differential pressure was seen across the 68B check valve during pressure increases.

Pressure equalized around the 68B check valve during stea5y' state .

coru$itions. h suggests that the check valve does not prevent small leakage but weuld function to prevent an intersystem I4CA. l

' Ca *2e leakage through the closed M01001-29B and 28B valves was calculate $ at .33 gpm at 975 psig. his is the flow rate that was causing the alarm initiation on Friday, April 11, 1986. % e mecsured leakage of .33 gpm is well within and represents no challenge to the relief capacity of PSV1001-22B. % erefore, Da concern exists regarding overorenmurintion At Abia. leakage Inte..

Se high pressure water test was performed on 'A' RHR injection line for two reasons. Se primary reason was to determine the actual outleakage on the

'A' loop in the normal operating corrlition. We second reason was to provide quantitative evidence that the 'A' loop was not the source of the pressurization events. Se results of the 'A' loop water test were

Pressure equalized arourd the 68A check valve at steady state conditions. 21s suggests that the check valve does not prevent minor leakage but would function to mitigate an intersystem IICA.

Re leakage rate thru the closed M01001-28A valve was 0.068 gpm. Ois l

rate is, through one closed valve, approxirrately one-fifth of the 'B' )

L system leakage rate through 2 closed valvas. @ is result proves that {

the 'A' systen is not the source 'of outleakage and that the M01001-28A ]

is a very tight seat. We 'A' loop results in comparison to the 'B' i loop results imlies that it is. possible in imrove the. seating l ability Rf. the..'D.' 1999. valves. Water testing data and results are contained in Apperdix H of this report.

1

4 RHR TASK FOICE REPORP (continued) Page.8 INVESTIGATION (continued)

D. Air Leakage Air leakage through the 68B check valve was measured to be 76 SLM at 45 psig. . Sere is no absolute criteria for this valve because it is not considered a primary containment isolation valve. Se test did prove that the 68B was seated because pressure was maintained in the test volume.

Appendix J tests on valve M01001-29B resulted in a leakage rate of 1.0 SLM at 45 psig. Tests on valve M01001-28B resulted in a leakage rate of 1.5 SIJ4 at 45 psig. Both of these values are well within the acceptance criteria of 7.89 SLM at 45 psig, and in fact, indicate the valves are tighter now than they were during the FO #6 LLRT when the 28 and 29 valves had leak rates of 1.9 and 0.1 respectively. It should be noted that the torque values of both

, valves have been increased which could lead to these inproved rea31ngs.

l Therefore, Da concern exists reoardino tbg ability Qf tbggg valves 12 magt, containment leakage critaria. Sese results also prove that the event of 4/11/86 was not an indication of a true containment isolation valve failure.

The leakage rate on the motor-operated valves also demonstrates that no ~

repairs are necessary for M01001-29B or 28B to meet established Apperdix J leakage criteria. We inability to quantify high pressure fluid leakage in operation resulted in the unit shutdown. Air leak test results are contained in Appendix I of this report. _

E. Research Efforts ,

Information and Evaluation of PNPS ard Industry Information A listing of documents reviewed by the R$R Task Force is containd in Appendix L. Salient results of Research ares l *2e motor-operated injection valves for RHR, 29s and ',8s were cycled in excess of 62 times for surveillance between Novewr 1984 and February 1986. It is a conclusion that this reper'ed cycling may have contributed to praature wear on the Valve 28B seat and the result has been seen through pressurization in 1986. D e same conclusion holds for 29B. The torque switch settings for both valves were increased in 1986 on February 15 for M01001-28B and on April 10 for M01001-29B.

The increase in torque switch setting may have increased the seating characteristics of the valves resulting in Local Icak Rate Test results lower then the EO 86 startup values.

The actual alarm on PS1001-74B was found to be at a system pressure of 365 psig. The setpoint, accozding to calibration records, is 394 psig.

The alarm actuation at 30 psig lower than necessary increases the frequency of high pressure alarms.

'n .

>g 1

)

i Mm MSK FOICE REPORT..(oontinued) Page 9 RESEAICH EFFORTS '(continued) '

2e maintenance history for. Valve M01001-22 shows that the valve !

-itself has never been disassembled. Se motor operator for M01001-28B: l

'has seen several maintenance activities. .In Decenber 1984,' prior .to l startup from IFO 6, MQ1001-28B had grease contamination of the notor and j spring pack of its Limitorque SMB-5 operator. Oil, from grease con- J tamination, was again discovered in Septenber 1985 when Equipuent j

.s Qualification (EQ) refits were performed. S e motor for the SMB-5 1 operator was replaced at the time of EQ work. Valve seating motor current was left at 100 anps when EQ was completed. .i When investigations were performed in February 1986 on the pressuri-zation problem, the as- fouM seating current:was 75 anps. An adjust- ..

ment to 90 anps was attenpted, but the seating current was not repeatable. Since a variation in seating current was an abnormality not previously experienced, the SMB-5 operator was disassembled.

' i Nothing was found wrong in the SMB-5 operator. W e operator was reassembled and a torque switch setting was made to provide a valve 1 seating current .of 105 anps. The 105 ' asp seating current was tested *

'I and found repeatable. Se M01001-28B was tested for seating current i on May 4,1986. Se current was found at 55 anps. We lack of repeatability of seating torque could be a significant finding with '

respect to root cause of M01001-28B seat leakages.

x i

.." ~ The maintenance history of the four ami injection path motor operators is contained in Appendix N of this report.

%e 1001-68A and B check valves were refurbished as part of the.Becirc pipe replacement project. . Appendix.O contains the documentation concerning the refurbishment of 1001-68B. his check valve was a rebuilt after chemical decon had been conducted. %e internals were i therefore very clean and easily inspected. The seating surfaces were examined under SX magnification and only a light lapping was q reconnended. Se seating surfaces were acceptable after lapping. It i is noteworthy that after 14 years of service, the condition of the check valve only required minor maintenance. Se valve was reassembled using new packing and gaskets.

IX. INFLUEtCE & MIR LEAKAGE ON OINER_RHR. SYSTEM PROBLENS During the past few months, a nunber of problems have occurrM in thn Mm system. The team attenpted to identify any correlation between events. %e !

events considered were: 1

Loss of seat stellite on Valve M01001-36A I

!-

Leakage of MIR head spray line j

[ *1-inch test connection failure between 1001-33B and check valve 1001- !

p 68B l

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( _ _ _ _ . _ _ _ _ _ _ _ _

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iRHR1TMK FOICE Rl! PORT (continued)) Page 10l hm (oontinued)'

The increased pressurization of,the RHR line led to increased usage of the '

M01001-36A valve to relieve the water in the line. MO1001-36A was used extensively to relieve.RHR system pressure and repeatedly for Torus cooling in 1986. . - Re . 'A' loop of RRR was used for Torus cooling in excess of 377 hours0.00436 days 0.105 hours 6.233466e-4 weeks 1.434485e-4 months ~in' thisL cycle to date. . Torus cooling flow rates are 2000 to 4000 gpm.-

21s repeated severe throttling service likely caused or at least contri- 3 buted to the damaged seat segment ard body erosion recently notad in the M01001-36A' yalve. l A more likely scenario is that use of the M01001-36A valve to clear.the RER high pressure alarm resulted In the formation of air pockets in the head l

spray .line and contributed to the occurrence of pressure pulses / water hanners in that 'line. Reference the cause analysis presented in PDC 86 , which is included as Appendix M.- .2e 36: valve discharges below the Torus.

levelt however, when the valve is opened to relieve system high pressure, a vacuum will' develop in the upper portions of the system. 21s will tend to draw in air through valve packings. If this trapped air'is not properly vented,. it can contribute to water hamner events. Rese pressure pulses /

water hanmers caused the head spray' failure. It should be noted, however,

~that. the' head spray failure was the result of a long period of pressure pulse / water hanner going back many years. Se letdown of system pressure accelerated failure but was not the sole cause.

i

,g Se 1-inch test connection failure was discovered in the January 1983 hrbine outage. Ris test connection is. located in the drywell inboard of the 1001-68B injection check valve. Se test connection exhibited fatigue failure in the ~ heat-affected zone above the sock-o-let weld. h is information conbined with walkdown'information of 1001-68B hinge pin ;

leakages, points to the prese,nc.e of a vibrational cordition in the line. . .!

The cause of the vibration may be from the B recirc punp, which had sustained a bearing failure, or from another phenomena such as 1001-68B disk oscillation.

X. EDCff CAUSE ANPMSJS_,

Mmuccatos The RHR pressurization problem can be viewed from two perspectives.

A) From a chronological approach, the cause was analyzed by examining the factors that could have contributed to a change when the trend in pressurization deviated from normal. B) An approach that considered the variables unique to the 'B' RHR injection versus the 'A' RHR system was used to analyze system outleakage. Both approaches.are based on the Task Force's determination that RHR systen pressurization was caused by boundary valve leakage from the T RHR injection line. 21s conclusion is presented in Sections II, III, IV and Appendix C.

The results of the two methods are both presented because interrelations )

exist and common cause may be present. y a

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_ _ _ _ _ _ _ _ _ _ _ Q

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NHR TASK FOICE -(continued) Page 11--

IOOT CAUSE ANM2 SIS (continued).

- A) CHRONOLOGICAL ANMXSIS -

Followingjan' approach taken from Kepner-Tregoe, the onset of RHR- =l pressurization events was decided to be a startpoint for a deviation from !

normal condition. :. Research into this deviation is presented in Section VII of the report with supporting documentation contained in Appendix F. Figure 5,- the plot of RHR pressurization events versus time, is a major tool in 3 this analysis. . Figure 5 shows that prior to Septenber 9,1985, .;

pressurization events are infrequent with only 27; occurrences out of 243 days. This is an occurrence rate of lit.- In Septenber 1985, the occurrance !

. rate is 15 out of 30 or 50%. ' he occurrence rate for Novenber is 70%, l a Decenber is 254,- January is 80%, .and February is 57% . October's data is !

incouplete because of a missing chart, but the available data is a 60%

occurrence rate. - his is a statistically significant change and'is determined to be that September 1985 is the point of deviation from normal. 3 Se exact date' of deviation is Septenber.9,1985. ne station had just #

. begun a power increase after the' September 1-8 outage.

Additional examination of Figure 5 also shows a correlation between startup

- from unit shutdowns and 'an occurrence of RHR pressurization events. In the.

-January through Augunt 1985 period,-there were 6 startups, 4 of these startups 'had RHR pressurization events occur within 1 to 2 days afterward. .

Although the sanple zis'not' large, the rate of correlation' is 75%.

. Se root.cause of RHR pressurization' ev'ents lies in the answer to the

- question."What happeneS just prior _ to or during the Septenber 1 to 8,1985

~

outage?" ' Prior to the Septaber 1 outage, drywell leakage frcan the floor f y ,

sunps was increasing.- Sere was.a severe coastal storm that had struck that had fouled the' main cordenser and contaminated the switchyard with salt t( 1 spray. We ' reactor power had been reduced to backwash the condenser and to

G .l wash down the switchyard. . At'0520 hours0.00602 days 0.144 hours 8.597884e-4 weeks 1.9786e-4 months the ACB104 arced over during T i washdown. his- resulted is' a load rejection. Since power was 1ess than )

45%, the automatic scrm function was bypassed, but reactor scram resulted )

from reactor high pressure when the turbine bypass valves could not handle l the uteam flow. '

Concurrent with this shutdown, the observed increase in drywell unidentified )

leak rate was discovered to be o seal failure on the 'B' recirc punp.

Activities related to the RHR syste for this shutdown and their potential effects are:

Recirculation Punp B Seal Replacement. We punp is isolated and drained for seal replacement. Were is a potential for air entry into Abe system which could propagate to the 'B' FHR injection line. This activity was performed twice in this cautage. /

i

___________m_ _ _ _ _ _ . _ _ _

I ll RER MSK FOfCE REPORT (continued) Page 12.

10Cff CAUSE ANALYSIS (continued)-

2e 'ARHR loop was used for shutdown cooling for this event. Bowever, the operating. logbook nantions that Procedure 2.1.7B, an opening flow test for check valve 1001-68B, was performed. Eis test is requird-by the IST program and causes the check valve to be bunped open using a flow rate of 4400 gpm. Sis operation disturbs the seating condition of the check valve and may leave the valve off it's seat. Water testing proved that pressure will equalize across the check valve, and as reactor pressure increases, this situation allows greater volume of pressurized fluid to act against the seat of the closed 28B valve. 21s could allow increacM 1eakage.

Possible B;tDi Cause Consideration 1 '

2e physical arrangement of the piping between the 'B' recirculation

. pump discharge line and the 'B' RHR injection line is shown on Figure 6.

Essentially, if air entered the system as part of the recirc seal replace-ment, any air present should have been vented through the punp as part of refill. Any non-purged air should have traveled out of the punp and risen up the discharge line. At the point where the RHR line ties in, trapped air .

would have ha3 to travel horizontally into the tee rather than continue-upward. . From a trapped air standpoint, the recirc seal replacement is not considered y

a viable cause for RHR outleakage,

2e act of unseating the check valve has definite implications in a A possible cause of RHR system wtleakage. .If the volume between the M01001-29B and 28B is not couplotely vented, the condition is nultiplied. W e pipe run between 283 and the drywell penetration is a local' highpoint because the.

pipe rises through the 23 fE elevation floor and runs horizontally at an elevation of 30 f t. to.the drywell penetration X51B. Inside the drywell, the pipe drops down to Elevation 20 ft. 21s local high point is not regularly ventedt the only possible vent point has' a pressure gauge installed on its test connection. It is therefore conceivable that air got trapped in this pipe run. When the check valve is unseata! or allows leakage past the seat, the pipe volume outside of the drywell becomes pres-

-surized. If air is present in the line, the compression of this volume can act as an acdanu1~ator. 21s action can have two effects. When the air accumulator " springs'back", pressure forces act against the 28B valve seat which may create more leakage and degrade lhe seat. Also, the 68B check valve is burped open allowing even more leakage'to occur.

From the standpoint of a possible root cause of 'B' loop RRR pressurization events the unseated check valve coupled with air entrapment is viable. In ;

response to a question of why this does not happen in the 'A' loop, the response is maybe it is and the 28A valve seat is not yet degraded enough to exhibit the pressurization. Secondly, the answer is that the 'A' loop is used extensively for shutdown cooling and trapped air is swept out of the pipe with the flow rate.

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RRR TASK FOICE REPOIE (continued) Page 13' B. . Variables Analysis other documentation and data has confirmed.that the RHR system inleakage existed only in the %' RHR injection path. The root cause of leakage into the low pressure system is because the boundary valve (s) allowed seat leakage to exit the high pressure. boundary. Se root cause of

-seat leakage is not easily determined. here are several variables which enter into the possible caises o ne number of valve strokes experienced by the valve.

o De amount of flow or service the' valve has experienced.

o me torque for closure and the motor operator type.

o The materials used for seat and disk construction.

, o Background environment of - temperature or vibration.

.o De type of valve.

. o 2e quality of the fluid passing through the valve.

o D e maintenance history of the valve.

o ne maintenance history of the motor operator. i

. De RHR system injection path is conposed of 2 loops which use identical ,

couponents in a nearly-identical configuration. De configuration differences are minor. For instance, the 'A' loop rises 3 feet higher prior to entering its recirculation pucp discharge point. At the point when this prcblem became visible,- the boundary valves in use were Mol001-28A and -

M01001-28B. Leakage existed through the 28B valve aM not the 28A. High

- water pressure test data has shown that, the outleakge from the 'A' system 9 is .068 gpm with only M01001-28A as a boundary. Se 'B' system had an outleakage of .33 gpm with 2 valves used for boundary, the M01001-29B and M01001-28B.

Se variables listed will be compared for the M01001-28B versus M01001-28A.

o Nunber of strokes for surveillance are approximately the samW 28A, in fact, has hai more strokes when service use is accounted.

! o Sarvice for the 1985-1986 period: 2e 'A' loop has been used for shutdown cooling for every shutdown except for the head spray arx3 MO1001-36A outages. Also, the leakage problem existed prior to these outages. Shutdown cooling service puts flow rates of 2000 to 5000 gpm through the injection path valves. Pilgrim's operating history indicates an exclusive preference for use of the 'A' system for shutzlown cooling. Derefore, since service timo and flow is

( biased to the 'A' system, this variable would inply that service is not the cause of degradation in 28B valve.

o Se torque required for valve closure torque switch settings have been increased for 28B. For 28A the 1985-86 torque history is that torque switch settings on the SMB-5 operator has remained the same.

This variable supports the conclusion that M01001-28B malfunction is !

the root cause. ,

o The materials of construction for 28A and 28B are identical.

I

/

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~ _ _ _ _ _ _ _ _ _ -

RHR TAS4 FOICE REPORP (continued) Page 14-VARIABLE ANALYSIS (continued) o he environment of the' valves has differences. Se M01001-28B valve l is in the same room as the HPCI MO23014 valve. Valve MO2301-4 is I normally open with reactor steam -in the line. .2e %' valve rom is !

physically smaller than the 'A valve room and there is less venti- 4 lation. His makes the area temperature higher which may have an !

effect on the M01001-28B. valve with regard to observed grease -)

contamination.- 1 1

There is evidence of vibration inside the drywell as exhibited by the failure of the 1-inch test connection on the %' RHR line.

Vibration measurements taken as part of the recire pipe replacement.

startup, however, indicate' the 'A' recire loop has marginally higher ;

vibration levels. Since the RHR injection lines tie into the'recirc !

loops, there may be an induced vibration, but data indicates that 2 the 'A' RHR injection line .would be higher. Vibration in the %' !

racire 'line may have changed as a result of the %' recirculation puup bearing -failure in early 1985.

From a local temperature standpoint, M01001-28B may be subject to i degradation because of the thermal effects of grease thinning. Se 1 vibration data would indicate a problem in the 'A' system but these .

measurements are relatively old and may not represent a current-condition. ~

{A o Both valves are 18-inch globe Valves of the same model and manufacturer.

] \

o ne quality of fluid passing through the valves should be equal. ~l Both systems are supplied from the same sources - keepfill and Torus. Dere may be a potential that the 'A' system water has less .

contaminants from stagnation because the 'A' loop does see more use for both shutdown cooling and Torus cooling.

o Se maintenance history for the valves is as tabulated:

-Both 28A and B have never been disassembled.

-Both 28A and B have had their packing leakoff cut and capped.

-Both 28A and B have had packing replacement post LLRT.

With respect to the valve internals, both have seen similar repair at similar frequency. Both the 28A and B valves have a relatively good local leak rate history (See Appendix L). Since no fundamental differences exist in valve repair, this variable does not account for root cause.

I i

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l 3

Mm TASK FOICE MPOIC (continued) Page 15' VARIABLPS.RBLYJJE (continued) o Motor Operator - 2e M01001-28A and B valves both have Limitorque 94B-5 operators. %e 28A valve has had a problem with gear meshing !

(12/22/84), an inleakage problem (the reactor was receiving Mm in- l 1eakage while shutdown), 20 modification for PDC 84-60 and valve actuator reorientation for EQ flooding concerns. W e 28B valve has had grease contamination in the motor operator and spring p mk; the motor was replaced at the time of EQ work when grease was again found in the motor. We 28B valve has exhibited inconsistent closing current values. When work was performed in February 1986 .

to mitigate MIR outleakage, the as found seating current was 75 l anps. An attenpt to increase the seating current to 90 anps was l unsuccessful. %e seating current was erratic and would not con-sistently remain at 90 anps. Se motor operator was disassembled ,

nothing abnormal was found. When reassembled, the seating current was set to 105 anps on February 14, 1986. We seating current was checked again on May 4,1986. It was found at 55 anps. We grease contamination of the motor coupled with the unaccounted for relax-ation of motor seating torque is an anomoly that inplies that the ,

28B valve may not be performing aSequately. %is is considered viable as a root cause with respect to Mm system pressurization.

The variables that could account for a difference in the leakage chara:ter- .

istics between M01001-28A and 28B are:

6 .

' -Closure torque

-Environment

-Fluid quality

-Motor operator history The corclusion of the variables analysis for root cause is that M01001-288 has a greater leakage rate for water than M01001-28A because of environ-nental and motor operator repair history. The problem may lie in the motor operator or in the valves' internals.

C. An alternative to the analyses presented is to state that the leakage exiting the 'B' Mm loop is acceptable at .33 gpm. %e pressurization of the system is manifested because the low pressure system has been trade tighter. Because of reduced system cutleakage as evidenced by valve packing observations and the demonstrated tightness of the Mm punp discharge check valves an3 overall system, the minor leakage past the isolation valves resulted in system pressurization. Alarm annunciation at lower system pressure than setpoint contributed to the frequency of cccurrence. It is possible that the conbined effects of decreased system cutleakage coincident with gradual valve seat wear have lead to the cbserva3 increase in Mm system high pressure alarne.

It should be noted that there is no evidence of parameters being outside Tech. Spec. limits and all systems operates properly to eliminate the alarm condition. Ha3 the alarm not operated or had the operator failed to rea:t, there are pressure safety valves in the system which are set to open at 428 psig. Each valve has a relieving capacity of 54 gpm at 500 psig.

?

- RHR MSK FORCE REPORT '(continued) Page 16 i

XI. RECGelEtOATIONS

- Se RHR pressurization problem has been defined and root cause has been

- proposed in prior sections of this report. Ibot cause is.either valve degradation of the Mol001-22, . improper seating of check valve 1001-68B-coupled with improper local venting or a combination of both. . . .

Alternatively, the problem can be viewed as acceptable if mitigating a, measures are taken.

Management is presented a decision regarding the RER problem. Se decision can be made that either the leakage from 1001-28B is unacceptable l

or that the leakage is acceptable. Sere is no definite regulatory criteria l available because Local Ieak Rate (Appendix J,10CFR50) leakages are accep-table by a significant margin. Wree sets of reconnendations are presented, one for each branch of the decision block and one set that remain ccamon to

. deal with future issues. .

i

. A. If the .33 gpm leakage from the Mol001-28B valve is determined to be J unacceptable when compared to the .068 gpm from M01001-28A:

1. Evaluate _ the motor operator for M01001-28B to determine the cause of -inconsistent seating current. Valve disassembly is recom-mended only to evaluate the valve seat characteristics if motor operator investigations warrant such action. .

[ 7. OR 2. Disassemble and repair 1001-29B to ensure its leakage will be less go than .33 gpm in lieu of M01001-28B disassembly.

OR 3. Disassemble and inspect check valve 1001-68B for evidence of seating and oscillation. Valve 68B is the first obstruction from the pressure source and may be a cause contributor.

OR 4. Similar degradation may be occurring in the 'A' RHR loop. It ir optional to expand these recommendations to the 'A' system as weh.

B. If the leakage exiting 'B' RHR loop is determined to be acceptable:

1

1. Mitigate the effect of the leakage by allowing a controlled amount of leakage to exit the system. A suggested method is to open an RHR discharge check valve bypass valve (1001-100A, B, C or D) a specific and controlled amount. %is would allow a known leakage to '

return to the Torus. If the seating of RER valves further degrade, the amount of leakage to pressurize the system will be known. A decision for additional action can be made when this occurs.

OR 2. Valves in this system originally had packing leakoff lines installed. Sese lines have been removed for Appendix J leakage concerns and for outleakage control. Reinstallation of the packing

, leakoff could be re-established if an Engineering analysis l

supported such an action.

I l 1

_m ____-m___m.__m_ _ _ _ _ _ _ _ . _ _ _ . .

RHR SSK FOICE REPORT (continued) Page 17

~

RECONDDATIWS (continued)

C. Recommendations Comon to Either Decision 2e following recommendations are in Mdition to Beccanendation.A or B and each should be resolved. We recomen3ations are expressed as safety and operating concerns.

1. C0tCEIN l 68B (A) check valve can be enployed to mitigate Intersystem I4CA events in the RHR system.

Check valves are not periodically tested for degradation.

Check valves have no closure verification test.

RECOME2OID nm

a. Provide for an acceptible startup seating test / verification of both 1001-68A and B when shutdown cooling is secured - A trial procedure is requird prior to startup from CAL 86-10 outage. ~

OR

~

b. Perform 1/Befueling Outage leak test on 68's for pressure drop

~

s capability - This is to be initiated in IFO 7.

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c. Replace /rdesign check valves to provide positive position indication. (%is is a long term item anS should be based on a neM s evaluation).

2. pf

%ere is no system pressure rnonitoring or trending capability for severity assessnent.

EECOME2OED nm

a. Install additional pressure gauges in system: between 28 and 29, and outboard of 28 - prior to startup from CAL 86-10 outage.

3. COCERN MIR system overheating (potential steam void formation in leakage path) and inadequate system venting.

9

RER TASK FOICE REPORT (continued) Page 18 RECOME20ATICES (continued)

EglONE20ED ACTION

a. Develop system venting program - including adequate vent location for local higtpoints - and method to control by results -

concurrent with startup from CAL 86-10 outage.

b. Provide metris for systtra temperature monitoring - concurrent with CAL 86-10 outage.

J

c. Remove pressure gauge installed on RHR injection line to allow for a vent path - prior to startup from CAL 86-10 outage.

4. CCtCERN Cperating practice may have lead to event. "

RECONE20ED ACTICN Wo system operating practices are considered cause contributors to Q pressurization events. We following changes are reccarended:

a. IST Program opens both 68A and B check valves once per quarter if in cold shutdown - change frequency of test to once per refuel.

This action is long term because the IST Program relief may not be possible,

b. Excess stroke of 28 & 29 isolation valves - Reduce frequency of test. 1001-28B, 29B were stroked 62 times between 11/84 ard 2/06.

nis action is long term because it requires extensive nch Spec changes.

5. CCtCERN 2e alarm procedure does not provide action to assess and correct leakage.

RECOME20ID ACTION

a. Revise procedure to allow for control of repressurization and to provide additional assessment and corrective action concurrent with startup from CAL 86-10 outage. Action from correrns 2 and 3 must be conplete. This action is dependent upon instrumentation.

L' t

i l

! , RHR TASK FOICE REPOIE (continued)l Page 19 RECOMENDATICES (continued)

6. ; CCECERN 400 psig injection permissive - If undetected failure occurs, there-is no protection against simitaneous opening of 28 and 29 valves.

RECOMEtDED ACTION Trend surveillance history for reliability. !here is no inmediate /

need for actionyresent surveillance tests are considered adequate.

.XII. RESTM6 ANMESIS Local ' leak rate testing has been conducted ar/ results for the RHR ,

, injection -line are 1.5 standard ' liters per mirm.e (SLM) for M01001-28B and 1.0 Sm for M01001-29B. - 'the acceptance criteria for Appendix J is 7.89 Sm. - .]

'l Q1 an individual basis, both valves 'are acceptable as is. .On a total i containment leakage basis, the. least pathway analysis of 1.0 SLM containment leakage for the 'B' . loop of RHR is acceptable. No failure of containment "

has occurred and Tech. Spec. 4.7.A.f(2) and (3) are met. From a containment - ;

integrity standpoint, the unit is acceptable for restart.as is. '

From the standpoint of a concern over RHR system pressurization and integrity, the measured water outleakag,e from the RHR line of 0.33 gpm is not a hazard when compared to the design overpressurization relief capacity of 54 gpm for each of 2 pressure relief valves. Associated effects of leakage,'such as overheating of the piping, can be monitored and actions can be taken for correction. 'Ihe Task Force has made recernmendations associated with a decision on the accept &ility of the 0.33 gpm. 'Ihe leakage is correctable with maintenance on the valves or the leakage can be mitigated by allowing a leakoff.

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APPENDIX A RHR 1986 CHRONOLOGY

-Key: z(OS) Operating Supervisor'slLog (1/1 thru.4/14)

-(WE) Watch Engineer's Log (1/1 thru-4/12)

(ST). STA Log (1/1 thru 4/12)

(RW) Information provided from Radwaste (SD) ' Shutdown

-(MR) Maintenance Request .

(F&M) Failure'and Malfunction Report

'01/01/86- - *** Mode Switch - RUN ***- l 01/02/86 0006(0S) L"A"lRHR in torus cooling. ((HE) for chem lab sample).

0905(05) Secured "A"'RHR pump from torus cooling. q 01/04/86 '

0749(05) *** Mode Switch - STARTUP ***

1130(05) RHR. injection socket weld on RHR line between.H033B and-testable check found' leaking. F&M 86-05 and MR 86-12' issued. .

1615(0S) Completed zinc flush for RHR system. . Unable to open' I M0-1001-50 valve. Electricians investigating probable cause.

1815(0S)

~

Issued F&M 86-06 on MO-1001-50: inboard shutdown -4 cooling valve. Issued MR 86-17. Valve would not open.' ((WE) maintenance got valve open.but still investigating). ((ST) Overrode limit switch and valve '

opened - suspect water in switch or Drywell).

1830(OS) Established shutdown cooling mode of "A" RHR.

t 2250(05) *** Mode Switch..- REFUEL ***

1600- Tagging out M0-1001-33A for weld leak still 2400(WE) draining. (MR 86-.18) !

01/05/86 2400- "A" RHR in S/0 cooling. Head spray vents open 0800(WE) welding socket weld leak. 1 0818(05) *** Mode Switch - STARTUP ***

0930(ST) Made inspection of "A" RHR Quad for leaks. Found small jf packing leak on M0-1001-43A and grease dripping out of l MO-1001-18A. MR 86-23 issued to check and/or repair.

01/06/86 0630(ST) I&C starting to test drywell door seals prior to I starting work on MO-1001-50. '

0735(05) Secured "A" RHR pump from S/D cooling. '

0830(05) Placed "A" RHR into S/D cooling.

1005(OS) Removed "A" RHR from S/0 cooling.

0800- Completed work on M0-1001-50 & 18A 1600(WE) 1940(05) *** Mode Switch - RUN *** .)

1959(05) *** Mode Switch - STARTUP *** l 1

01/07/86 0840(0S) *** Mode Switch - RUN *** !

0844(0s) *** Mode switch - STARTUP ***

0855(0S) *** Mode switch - RUN ***

PAge 1 of 11 i 1

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J 01/09/86 0004(05) Put "A" RHR ruop in torus cooling. 1 0802(0s) -Taking "A" RHR pump out of torus cooling. -

01/10/86 1830(0s) I&C completed 8.M.2-2.10.2 Loop Selection Logic System B.

01/11/86 0300(05) 8.5.2.1 - LPCI Subsystem Operability Surveillance Test ,

0302(05) 8.5.2.3 - LPCI Motor Operated Valve Operability Test l 01/13/86 0018(05) Placed "A" RHR in torus cooling in order to transfer some torus water to radwaste. ((RW) 14,000 gal) 0027(05) Secured "A" RHR pump from torus cooling.

01/15/86 1500- Reviewed F&M 86-15 (MR 86-53) on MO-1001-29A control 2300(ST) circuit. Circuit found with blown fuse'(Control panel lights out). Investigation by electrical maintenance and NED revealed that a solid link '

~

. should be installed for F-10 series fuse list and l E-5000 series. Control room drawings MlH series j show a fuse in this circuit. Further evaluation -

will be conducted by NED. I 1640(0s) "A" LPCI valve M0-1001-29A inop. , i 1900(0S) Via phone call with NED, LPCI system is operable l with fuses in control power circuit but not by design. Paperwork to follow in the AM. Notified NRC. _

l 2111(ST) Inspection of control circuit for M0-1001-298 l

revealed a fuse the same as MO-1001-29A. Replaced 1--

with a solid link. F&M 86-17 (MR 86-54) submitted.

1600- F&M on MO-1001-29A valve. Lost light indication 2400(WE) fuse for control power blew. Investigation of points show a link not a fuse. Replaced fuse under 3.M.3.8 (Inspect / trouble shooting-electrical circuits) timed valve, in spec. Declared A-LPCI loop inop until Engineering evaluation. Replaced link and ,

Engineering CQI to validate and certify link. Doing this makes "A" LPCI loop operable per Engineering via phone call with NED-John Pawlak the system is operable with the fuse in the control power circuit but not by design. Paperwork to document this to follow in the a.m. 1/10/86. MO-1001-298 had fuse not a link changed out fuse to link.

01/16/86 0002(05) Placed "A" RHR pump in torus cooling for Radiochem lab.

2246(05) Rx scram.

2246(05) *** Mode Switch - STARTUP ***

i 01/18/86 1106(OS) *** Mode Switch - RUN ***

Page 2 of 11

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K1/20/86; .1611(0S)f

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0 L8.M.2-2'.7---lCSCSpumpdischargemonitors.- ;

8.M.2-2.1.3:-LReactor Water-Level Containment Spray-

' Permissive.-.

1657(OS) .Placed "A":RHR~ pump in torusLcooling:iniorder to-send some torus water to.radwaste. -((RW)l8,000) z .

1703(05) . Secured "A"iRHR from torus cooling, u

I' J01/21/86o 0700-; . Reviewed F&M 86-22.on PS-1001-83A. -

1500(ST).

01/22/86 [2340(OS) Dropping? torus water to'radwaste- . ((RW).9,000)<

01/23/86 0001(0S) : Putting RHR"into torus cooling.for chemistry.

0808(0S)- Secured'from torus cooling. chem lab;got 'their-sample'.

r 01/24/86 1600(ST) Reviewed-F&M.86-22 on;PS-1001-83A'-(containment'high pressure switch) which failed to actuate on 1/21/86-surveillance.

1706(OS) 8.M.2-2.10.2 RHR Reactor Pressure' Permissive Loop Selection Logic Functional Test.

8.M.2-2.'10.'2-16 LPCI 8reak Det' Logic Functional Test. .

2030(OS)i Pumped .5K; from torus to RH via RHR.

01/26/86- 0740(0S) . Pumped SK.'of torus water to RW.

0920(ST)- ' Inspected A&B RHR valve rooms. Felt plpes; ,B loop -

hot Indicating check. valve' leaking. -In conjunction- ,

of RHR high discharge piping pressure alarm on 903. l I Check valve 1001-688 and MO-1001-288 apparently leaking. Pressure. sensor is upstream of MO-1001-288- :

valve. Informed H.E. Cycled M0-1001-288 valve. ;

Monitoring alarms to see if repressurization occurs. "j 01/27/86 0043(0S) 8.M.1-23 (manual ~ scram)~.

1 01/30/86. 0050(05) "A" RHR pump in torus cooling.

((HE) for Chem Lab Sample) 0858(05) Stopped "A" RHR torus cooling. !

01/31/86 0000- "A" Priority MR on "B" RHR Valve Room Door Latch. i 0800(WE) j i 02/02/86 1625(OS) Pumped 6K from torus to radwaste via RHR. i I

2/06/86 0010(0S) Placed "A" RHR in torus cooling for chem. (Note: )

WE log states "C" pump) !

0832(05) Secured from torus cooling for cooling sample. .j 02/08/86 1530(05) Started "A" RHR pump in order to transfer some torus water to RH. ((RW) 6.200 gal) 1540(0S) Secured "A" RHR pump.

0'2/10/86 0417(ST) Reviewed 8.5.2.2-LPCI Flow Rate Test "C" RHR pump in low alert. Notified W.E. and Compliance via form 8.I.3D-1. Required range 183.5-213.4 psig. Tested at 180 psig.

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)02/11/86: - '0045(05) Completed 8.5.2.3 - LPCI Motor- Operated ialve _

b ' Operability Test.

0320(0S)

' Completed.8.A.16'- RHR System Integrity Surveillance.

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.0321(05)' . Completed 8.5.2.1.- LPCI~ Subsystem Operability' 'I

' Surveillance Test.-

(0437(OS) . Completed 8'.5.2'.2_.- LPCI Pump Flow Rate': Test. ,

me" . . Breaker 604. trip,? loss:of B-20 MR84-46-512.

J ~0per 5 initiated due to PCIV' Inoperable,.

Unus'ual-@~1115. Cleared at.1117.'

-02/12/86 :1500 . Operations took up on M0-1001-28B' valve by hand 2300( ST ) -- results being assessed. ,

a 2 y s02/13/86l 0500(05) A" RHR pump in torus cooling.

((ST) for chem. lab ,

sample) 1 0802(05) . Transferred 6300 gal..of torus water l to RW..

r 0904(0S) Secured torus cooling modeLof "A"'RHRiloop.

1845(ST)- Surveillance started to inop_RHR MO-1001-28B

. ! val _ve-valve cycled by maintenance and-closed to 100-amps-limit switch'to.be worked-on in-a.m.~(MR-86-109) 1600-' _

Doing. surveillance for:LPCI sub-system Inoperable. i I2400(WE) Electrically seated M0-1001-28B' valve'at,1921 brs.

If alarm comes in tonite,-declare M0-1001-288 valve l

' inoperable and call M.-_McBride'at home otherwiss-i the valve will be inoperable at.0800 in morning-(after surveillance.are done.) .

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-02/14/86 0300(0S) Completed 8.5.3.3 - Containment Cooling' Valve V. -

. Operability Test.

't 0211(05) Put "C" RHR pump in torus cooling.

0845(05) 4M0-1001-288 (RHR/LPCI) valve made inoperable for-maintenance. ,

-1010(05) . Secured torus cooling mode of RHR- .

1032(-05) Unusual event-due to A diesel and M0-1001-288. 4 1232(05) Unusual event over. _

2130(05) 8.5.3.3 - Containment Cooling Valve Operability Test- ;

for LPCI inoperable.

a 1600- Installed gage between MO-1001-28A & 29A valves .

TM 86-06. 'l 2400(WE) ((ST) Pressure reading 1150 psig) i

02/15/86 0447(0S) 8.5.2.1 - LPCI Pump operability, i

'2220(ST) Reviewed 8.5.2.3 for MO-1001-288 valve. -Open 26.06 7l i sec, close 27.83-sec.

2225(OS) Declared M0-1001-28B valve operable and signed off MR 86-109.

1900- Reviewed 8.5.3.3 - Containment Cooling Valves 0700(ST) Operability Test.

, 02/17/86 0811(05) Received annunciator "RHR discharge on S/0 cooling section hi presure" - took appropriate action to clear annunciator.

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1303(05) ' Received-annunciator _"RHR discharge on S/0 cooling section bl pressure" - took appropriate action to clear annunciator.

1330(05) Declared the LPCI MO-1001-288 inoperable due to.

leakage past valve seat. Commence-procedure 8.5.2.5

, .( LPCI Subsystem inoperable) - F&M 86-36 and

'MR 86-115 issued. .

i 0800- .

Received h1 pressure alarm on shutdown cooling. l 1600(HE); Had electrician check closing torque (105 amps) notified McBride.

LPCI.Inop going to set torque to,125 Amps.

2125(05) Maintenance completed on M0-1001-288. valve. ;

(RHR/LPCI), M0-1001-288 valve;is closed and !

M0-1001-298 valve is open.

2259(05) Completed survie11ance 8.5.2.1 - LPCI. Subsystem Operability Survie11ance Test.

02/18/86 0615(ST) As of.this time, "B" Loop RHR high pressure has not

. alarmed (M0-1001-288 valve leakage indication).

0700-- Reviewed surveillance 8.5.2.3 "LPCI MOV operability 1500(ST) . Test" performed for past work test on MO-1001-288, results acceptable.

1205(05) -Completed MR 86-115 and declared LPCI MO-1001-28B .

operable.

1202(05) LCO 3.6.C.2 - 7 day on D/W sump.

1548(OS) RHR Discharge / Shutdown Cooling Suction High Pressure' !

Annunciator received. -

1550(05) NHE declared valve M0-1001-288 (RHR/LPCI)

A inoperable. NOM notified, MR initiated, F&M initiated. ( ( H E-) started 8.5.2.5-LPCI Subsystem j Inoperable).

1631(0s) NRC Region I (Mr. Ray Smith) notified via ENS line l that valve M0-1001-28B is inoperable and 7 day LCO 1 in effect. i 1822(05) Completed maintenance on M0-1001-28B, verified MO-1001-28B closed, and opened valve MO-1001-298.

((ST) 298 on 24 hrs operability check.) ,

2057(05) Completed surveillance 8.5.2.1, (LPCI Subsystem i Operability Surviellance Test). !

1600- When closing MO-1001-288, hold switch 3 seconds 2400(HE) after closed indication. At 1822 reopened MO-1001-29B and waiting to see if alarm comes in prior to declaring LPCI operable. j Placed caution tag on MO-1001-28B to make operations aware of 3 seconds closing after full closed indication.

Safety Evaluation #1918 on LPCI. If RHR discharge alarm comes in, cell Mathis for ORC to institute this evaluation.

l 02/19/86 0410(0S) Pumped 10K from torus to radwaste via RHR.

0800- Haiting 24 hrs on M0-1001-288. Time is up at 1822-if ,

1600(HE) RHR discharge h1 pressure alarm does not come in by l then-LPCI will be declared operaole.

1822(0S) NWE declared MO-1001-288 operacle, 7 day LCO is no l longer in effect.

1845(0S) Notified NRC Region I (Ray Smith) that M0-1001-288 operable and that we are no longer in a 7 day LCO.

Page 5 of 11

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i 02/20/86- .0011(0S) "A" RHR pump in torus cooling'for chem sample. !

L 0805(05) -Removed "A" RHR pump from torus' cooling. - T

l0800- I&C working on FR 1040-1 B Loop RHR total flow 1600(HE) appears to be working OK now.

2258(0S). . Completed 8.E.10 - LPCI System Instrumentation calibration.

'02/21/86' 0510(05)- Placed "A" RHR pump in suppression pool cooling.

1025(05)- Removed "A" RHR pump from torus cooling.

1736(0S) Pumped torus to radwaste'via.'"C" RHR pump. j

Remaining in torus cooling. ((RH) 12,000 gal.) j 2219(05) Took "C" RHR out of torus cooling.

l 02/25/86' 0800- .Two A priority MR's (86-140,141) on PS-1001-74 A&B' ~f 1600(WE) to calibrate RHR discharge alarm.

02/26/86 0540(05) Received annunciator entitled "RHR discharge.on-shutdown cooling hi pressure". Took appropriate action to clear alarm.

. 1407(0S) . RHR discharge / shutdown cooling hi press" alarm cleared by NPO.

1930(05) SR0; 86-24'to 2.2.86 - RHR System ,

86-25 to 2.1.8.2 - Safety Class 2 and 3 !

Hydrostatic Test Procedure .

86-26 to 2.2.125 - Primary Containment Isolation Control System 86-27 to 8.5.2.3 - LPCI HOV Operability' Test 1 86-28-to 8.5.2.2 - LPCI Pump Flow Rate Test - l 86-29 to 2.2.19 - LPCI System 4 86-30 to 8.5.2.6 - LPC1 MOV Operability from ASP !

1945(ST) Completed SRO changes with WE to reposition .

MO-1001-298 and 288. 1 2020(ST) MO-1001-29B closed (closing amps 15) and MO-1001-28B cracked open. Bled pressure to torus. M0-1001-288 position full open. Low pressure alarm came in for a few minutes then cleared when keep fill l pressurized. Hi point vent on "B" RHR loop to be opened to insure system is solid.

2020(05) MO-1001-29B closed and M0-1001-28B open per PEM in 1

instruction log book. l 02/27/86 0005(05) Placed "A" RHR in suppression pool cooling for chem lab sample. !

0905(05) Secured torus cooling. "A" RHR pump off. l 2300- Pressure between MO-1001-28B & 298 being monitored, i 0800(ST) Pressure holding at 100 psi. '

1415(05) RHR loop B pressure approximately 75 psig.

2142(05) Completed 8.5.2.1 - LPCI Subsystem Operability ;

Survie11ance Test. !

2200(ST) After completing 8.5.2.3 (LPCI MOV Operability Test) for "B" LPCI valves, pressure was at 270 psig j between M0-1001-28B and 298. Operations to check in j 1 hr to see trend. l 2230(ST) Completed review of 8.5.2.3 valve time for ISI and !

OK.

l l 02/28/86 2200(0S) Pressure between MO-1001-288 & 298 approximately 100. l Page 6 of 11 l :

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03/01/86 0640(05) Pressure between M0-1001-28B &-29 valve 1s 90#.

'1400(05) ."B" RHR loop.. pressure approximately 90 psig b~etween M0-1001-298 & 286.

1835(05) Pumped 5200 gallons of torus' water to radwaste.

'((RH) RW States 5,000) 2005(05) "B"'RHR pressure 110 psi between MO-1001-28B & 298.

, 03/02/86 0600(0s) Press.between MO-1001-298 & 28B is 110#..

1300(05) 'BRHR press approximately 90 psig between M0-1001-29B

& 28B.

2200(05) 110 psi between MO-1001-28B & 298.

03/03/86 0330(OS) Completed 8.2.6 - High Energy Piping Instrumentation Inspection.

0410(OS) 110# between M0-1001-28B & 298 valves.

1943(05) 100 psi between MO-1001-288 & 298.

03/04/86 0115(0s)- Putting "A" RHR pump into torus cooling.

. 0410(05) 105# between M0-1001-298 & 28B valves.

2201(05) 80 psi between MO-1001-288 & 29B; 03/06/86 2320(05) Switch "A" RHR pump and put torus suppresion pool cooling. .

0010(05) Drained 5700 gallons of torus water to radwaste'.

0320(OS) Completed 8.5.2.3 LPCI MOV Operability Test.-

0615(05) 250# pressure between M0-1001-29B & 288.

0815(05) Secured from torus cooling, chem lab got a torus -

water sample, j 2157(OS) 110 psi between M0-1001-28B & 298.

2300- Reviewed 8.5.2.3 LPCI Motor Operated Valve. i 0700(ST) ' Operability Test. Results satisfactory but 28A valve showed a 1 sec increase in opening time. i J

03/07/86 1000(05) 110 psi between MO-1001-298 & 29B.

1640(OS) Initiated oper 5.F due to pinhole leak in seamless i elbow on line to headspray (RHR) which can't be isolated.

1640(ST) Operator on tour discovered leak.in elbow of head spray line in torus room. Shutdown in progress to ] 1 repair. F&M 86-47 and MR 86-152 issued on same.

Visual inspection of head spray line show 3-4 i hangers broken, two 90* elbows (leaking e %ow and adjacent elbow) sprung open to approximately 110*. i Pipe section and elbow that enter pipe chase from l torus room partially crushed and deformed. Although !

the area could not be inspected at this time, it is ,

likely that further problems exist up the pipe chase.

03/08/86 0432(OS) *** Mode Swttch - STARTUP *** l 1120(0S) Placed "B" RHR pump in S/0 cooling. l 1356(OS) *** Mode switch - SHUTOOWN *** i 0800- Preparing to tag RHR loop "A" and drain for head 1600(HE) spray MR (86-166). ((ST) Review of root cause analysis for head spray line) 2300- Submitted MR (86-165) for hydro of "A" RHR.

0700(ST)

Page 7 of 11 l

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'03/09/86 0530(ST) Replacing. gaskets and tightening FE-1001-85 on' head

. spray line. ~ ,

NOTE MR-86-171, 172 issued on 3/9/98.

i 03/10/86 '0800- Started hydro on upper cap,

.2000(HE) 2130(OS) Took up-on packing on. 1001-33A valve. ((HE) leak stopped)

. NOTE MR 86-179 issued on 3/10/86.

03/11/86 2000- MR 86-180 on 1001-51. to check grease in gear box.

0800(HE) Removing insulation from piping to check weld at 18" pipe connection on RHR system.

0612(ST) -Tag out complete for "A" RHR hydro. Vent tags will be hung when purging system of air. Halting for results of x-rays to start-filling. 3

-1356(05) *** Mode Switch - STARTUP ***

. 1545(05) Placed NHE tags on M0-1001-60 & 63 head spray valves per PDC 86-20.

2125(0S)- Closed- 1001-53 valve due to leakage. Still draining down "A".RHR-loop via 34 and 36 valves.

03/12/86 0330(ST) Completed-Detagging, filling, and venting of "A" RHR loop. .

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.0426(ST) Started "A" and "C" RHR pumps.

0515(ST): Reviewed 8.5.2.2 and 8.5.2.3 RHR pump and valve operability.

0521(05) Completed surviellances 8.5.2 and 8.5.2.3 "A" loop -

RHR system operable.

-~6 0000- RHR-A Loop tagging cleared (double verified) and 0800(HE) was filled and properly vented in.all areas.

"A" RHR loop testing completed.

1020(OS) Remov'ed "B" RHR pump. ((ST) .from S/D cooling) 03/13/86 1710(OS) Started "A" RHR pump in order to drop torus water to R/H approximately 5400 gal.

0205(0S) *** Mode switch - RUN *** !

03/15//86 1905(OS) *** Mode Switch - STARTUP ***

{

03/16/86 0245(05) Placed "A" RHR pump in S/D cooling.

0353(0S) * *

Mode Swi tch - SHUTDOWN "*

i 03/17/86 2300- Reviewed 8.5.2.3 LPCI MOV Operability Test for"B" l 0700(ST) loop, i

03/18/86 2335(05) Completed 8.5.2.3 - LPCI MOV Operability Test j 0120(OS) Completed 8.5.2.1 - LPCI Subsystem Operability J Surviellance Test on "B" & "D" RHR pumps.

03/20/86 0720(OS) In torus cooling on "D" RHR.

1515(05) Secured torus cooling.

1600- "A" RHR in S/D cooling.

2400(HE)

Page 8 of 11

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L 3/24/86 1300- Retiewed F&M Surveillance.8.M.2-2.2.1-(Recirc system p 2300(ST) ' delta P for LPCI' selection) exceeded by +25'/. date.

103/29/86 0730(OS) *** Mode Switch - STARTUP *** !

1115(05) Took "A" RHR._ pump out of S/D cooling. ;

1125(05) Dropped torus water level to RW ((RW) 6500 gal.)- ;

, a

'03/30/86 0114(0S) Secured S/D cooling due to I&C surv.

'0128(05) "A" RHR pump back in S/D cooling. . .i 04/01/86 '0900(05) *** Mode Switch - RUN ***

- - Mode Switch - STARTUP.*** .

- - Mode Switch - RUN *** !

2304(05) Out of S/D cooling.

04/02/86 0900(05) Pumped 7500 gal of torus water to R/H.

1345(HE) Declared MO-1001-36A valve inop at.1345 hrs due to

, execessive leakage past valve. Issued F&M 86-79 j and MR 86-244. Electrical Maintenance will increase i

. torque switch setting. Surveillance 8.5.3.7 in l progress - one containment cooling loop inop. j 1350(05) Started 8.5.3.7 surveillance for one containment d cooling system inop (H0-1001-36A valve).

1620(05) Start "A" RHR pump in torus cooling to attempt to flush out M0-1001-36A valve. i 1645(05) Secured "A" RHR pump. 1 2040(05) Completed 8.5.3.3 (Containment Cooling Valve Operability Test) and 8.5.2.1 (LPCI Subsystem .

Operability Surviellance Test).

A 2047(05) Completed 8.5.3.7 - One Containment Cooling i Subsystem inoperable. )

1500- M0-1001-36A valve leaking by. Subsystem of j 2300(ST) containment cooling inoperable. (Torus spray and i suppression pool cooling). 1 Reviewed 8.5.3.3 - Containment Cooling Valve !

Operability Test with exception of M0-34A, MO-36 & 37 j and all other "A" side valves. '

, 04/03/86 0114(05) "B" RHR pump in torus cooling. ((HE) for chem lab I sample) 0000- Water level pertubation test.

0800(HE) 0820(05) Secured from torus cooling.

0800- Hold off water level pertubation surviellance until 1600(HE) some discussion is made on the unit as far as MO-1001-36A and turbine inspection.

1500- Reviewed 8.5.2.3 for "C" Pump.

2300(ST) Reviewed 8.5.3.3 containment valve times.

1600- A containment cooling subsystem inoperable.

2400(HE) (MO-1001-36A leaking).

HE Tag on MOV-1001-34A and breaker open. l 2132(0S) Completed 8.5.2.1 - LPCI Subsystem Operability ,

Surviellance Test for "B" loop only.

Page 9 of 11 l

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. Going into S/D cooling.

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04/04/84 0300(05) _

0700- Surveillance 8.A.2 - Torus to Drywell. Vacuum Breaker 1930(OS). *** Mode Switch - STARTUP ***~

1500(ST) Leak Rate Test done.

2029(ST) "B" RHR pump placed into torus cooling in preparation for starting HPCI. ;

04/05/86 0800- *** Mode Switch - SHUTD0HN ***

1600 (05) 0000 . Placed "B" RHR pump in S/D' cooling. Closed 0800(HE) H0-1001-53 caution tag.on M0-1001-19.

Maintenance working removing operator on MO-1001-36A-1600-- . ***' Mode Switch - REFUEL ***

2400 (0S) Opened M0-1001-37 to drain water from MO-1001-36A.

1600- .

Found approximately 5" piece. missing from-

. 2400(HE) M0-1001-36A. Plans are to grind out_and.make new one in shop. Should be approximately 2 days. 24 04/07/85 0000- _ Received call from D. Swanson about M0-1001-36A 1 0800(HE) valve minimum threshold. See memo.

0752(05) . Installing Temp mod 86-13 on M0-1001-36A valve. ;

2028(OS) *** Mode Switch - STARTUP ***

2242(0S) *** Mode Switch - REFUEL *** ij 04/08/86' 0907(0S) *** Mode switch - STARTUd ***

1616(05) Completed review of the temp mod associated with the M0-1001-36A valve with the watch. #

b 04/09/86 0435(OS) Completed review of temp mod concerning the M0-1001-36A valve and operation of mock up mode switch.

0940(0S) "B" RHR in S/D cooling.

1130(05) M0-1001-36A valve.

04/10/86 1209(05) *** Mode switch - RUN ***

1500(ST) Unit at 301. power. Electrical Maintenance looking at MO-1001-298 leakage.

Maintenance (electrical) torque up on 1600- _ l 2400(HE) HO-1001-298.

NOTE MR 86-273 was issued 4/10/86.

04/11/86 0246(05) Received S/D cooling - RHR discharge hi press. alarm.

0315(05) Received S/D cooling-RHR discharge hl pres, alarm.

0326(OS) Completed 8.5.2.1 - LPCI Subsystem Operability Surviellance Test.

0327(0S) Completed 8.5.2.3 - LPCI MOV Operability Test.

0336(05) "B" RHR in torus cooling for chem lab.

2300- Reviewed three 8.5.2.3 (LPCI MOV Operability Test) 1 0700(ST) Surveillance. On the first, the MO-1001-29B showed a large (approximately 3 second) increase in closing time, but returned to normal in two subsequent tests. ,

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, , ^4/11/86 1115(05) Secured from. torus' cooling. . .

1150(05) Pumped'9000 gal of torus water to R/W. .l-1158(05) Received alarm "RHR discharge high pressure".

1415(OS) Received alarm "RHR discharge ~high pressure".

Declared-LPCI inop,' starting surveillance 8.5.2.5 and closed MO-1001-28B. ((ST) suspect MO-1001-298

-0700-- leaking) "B" RHR loop in torus cooling mode for chemistry. . . .

1500(ST) ~ Status of MO-1001-29B valve will be observed when

.out of torus, cooling.- .

.1653(05) Received annunciator "RHR discharge on S/D cooling $

suction h1 press" with both MO-1001-28B & 298 shut.

Initiated oper 5 section.F.

1720(05) Proc 8.5.2.5 - LPCI Subsystem Inoperable.

-1954(05) Decrease to be increased 10% if annunciator comes.on-

)

again double rate of decrease.

, 2017(05) Notify NRC when alarm comes:in.(ENS) until cold S/D.

2215(05) Received alarm. ((WE). notified NRC) . j

. 1600- . Received call in conference with Region I and .i 2400(WE) Washington about current status. Got N.O.M. and got back to Conf. call.

Read log aoubt NRC notification.

Discussed with C.O.E. and he stated increase rate to

~

come down and if alarm comes back in to double rate.

(Info: Remember to put "A" RHR Loop into S/D cooling).

'l 04/12/86 0136(05) *** Mode Switch !TARTUP *** :

0645(05). Out of torus cool +ri 0' 0845(0S) 0908(0S)

"A" RHR pump in S/D cooling.

- - Mode Switch - SHUTD0HN ***

0908(WE) Out of unnusual event.

1 i

-l i

4 l

l

-q 1

I Page 11 of 11 i"_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . . __

- 2

.q.-

4

' APPENDIX A l

,7 1

~RHR'1985 CHRON0 LOGY' j

= NOTE: .The 1985. Chronology:is from the-Operating Supervisor's Log only, 1986l 4

is from aLvariety'of logs as noted by the key,at the beginning of ;j that-document.

1

'01/02-0104 L A1t'o S/D. cooling.

Oi/06 0910 'A.out of.S/D cooling. I LO1/06 .2052' A to S/D cooling.

01/07 1020' A'out of S/D cooling.

. 01/07 1200 A'and-C to S/D cooling.

01/d7 '1823 A out'of:S/D cooling.

O1/07 .1905 C out.of S/D cooling.

01/11- 0040 '8K to R/W (unknown loop)

01/11 1925-1957 Testing for HPCI inop.

'01/12' 0559 7.5K to RW (unknown. loop)

~

01/12 1335 C to Torus cooling

'01/12 1705 C out of Torus cooling 01/17 0115 A to Torus' cooling I 01/17 1102 A out of Torus cooling 01/19- 0330 Testing for HPCI inop ,

'01/20- 1520 8.M.2-2.1.7,8',9 01/31 0018 A to Torus cooling 01/31 0900 A out of Torus cooling 02/07 0130 C to Torus cooling 02/07- 1130 C out of Torus cooling

-02/10- L1430 Flushed-A in preparation for S/D cooling

(; 02/11 - 0130 A to S/D cooling

?

02/14' 0005 B to Torus cooling 02/14 0848 B out of Torus cooling L Started C pump S/0 cooling 02/15. 1605 f -- ---__---------------_______a

1 i '

y 502/17-: 1706 . Secured S/D cooling.

02/17 1730: . Torus water to RH thru A pump. -

s

02/17! 1748- Secured Torus!c'ooling.

02/18. : 1729' 'A' pump-water to RIN 1738' Secured i

, .1

~02/21 :0010- C pump to Torus, cooling 0820 Secured Torus; cooling

'02/28 . ;0007- Placed C:in-Torus cooling for Chem Lab 0915 Secured:

03/07 0126- -Started-A&C.for test 0140. Secured test. T 0212 .'MO-1001-36A inop-B&D.forftest 0656.

0701 Secured test 02/09 0429 36A - 22.7 close, 23.3 open 0900 36A operable ..

-03/14 2357. .A~RHR pump to Torus for sample -

1104 Out of Torus cooling 03/15 2350- Placed A RHR in S/D' cooling 03/16 . 13301 . Secured from S/D cooling for I&C 1342 A RHR to S/D cooling .

03/21 - 0000 A'RHR to Torus cooling for~ Chem Lab 0830' Secured from Torus cooling

'03/26 '1640 M0-1001-32-15 sec closed. Completed 8.5.2.1 for MR#84-10-278 03/27 2230 . Completed work on MO-1001-143A 03/28 0200 A pump to Torus for Chem Lab 1044 Secured from Torus 03/29 2300 Timed 1001-43C-87 sec open, 86 closed ,

04/01 0150 Started 8.5.4.5 (HPCI inop) 0730- Completed 8.5.4.5 i 1035 Stroked MO-1001-19 valve 61 sec open, 68 sec close 04/02 0615 Timed 1001-21 @ 16 sec close 1247 A RHR pump to torus cooling 1311 A RHR secured i 2121 7K to RW from C pump i

j l

L ]

o

04,/03 0300' Removed C pump from Torus cooling Fe i- _

l Placed'A pump to Torus for Chem Lab-

.04/04 0010 04/06 0418 ' 8. 5. 2. l '

0430 8.5.2.3 04/07 0017- -A.RHR pump to-Torus. cool 0327 Secured A pump 04/09 0220 Started A RHR pump-Torus to RW 0232 . Secured A pump 04/11 0030' A pump to Torus-cooling for Chem Lab .j 04/16 1030 Drywell Hi Rad Maint 1001-606A not working j 04/18 .0012 A pump,'to Torus'for Chem Lab- I

. 0838 Secured l 04/24 1145 While performing calibration check of PT-1001-601A (containment pressure Low Range) it was found that the transmitter was an absolute pressure transmitter versus a- '

required diff. pressure transmitter. 'A further check showed the transmitter for PT-110-6018 is also an absolute PT. Issue F&M. Entered 7 day LCO.

04/26 0400 'A pump'to Torus for Chem Lab.

-), 1120 SRO change 85-75 (PT-1001-601 A&B) i

). 1248 Secured A pump -

4 05/01 0044 A pump to Torus cooling.

0208 Secured A pump 05/02 0002 A RHR pump Torus for Chem Lab 0844 "A" secured Torus Cooling (A Pump)

~ 05/06 0115 8.5.2.3 05/07 1035 "A" started torus cooling 1120 Secured ]i l

05/08. 1437 "C" pump started for PASS l 2237 Secured

]

05/09 0956 "A" pump started for PASS 1343 Secured 05/12 2000 "A" pump started Torus Cooling 05/13 0045 Secured

-05/18 0010 "C" pump started for CHEM 1040 "A" pump started for CHEM 1050 Secured "A" l l

1

3 05/18 1300- "C" pump, started for CHEM 1 LOS/23' 0022 "C" pumpLstarted for CHEHL 1004 Secured 05/30 2355 "A" pump starte'd'for. CHEM 0856 Secured 0910' "RHR"' valve overload annunciator came'in when. securing-from Torus cooling.

0935- Investigation revealed-overload-relay tripped on 1001-34a possible motor-problem 06/03 1440 "C" pump started for PASS Testing

]

06/04 11118 "C" pump started for PASS Testing' 'I 1207 Secured ,

1315 "C" pump started for PASS Testing !

1456 Sacured 06/05: 0852- -"A" Pump-started for PASS. Testing.

'1004 Secured ,

1414 "A" pump IN ,

06/06 .0319 "A" pump IN 0524 Secured 0739 "A" pump IN-1310 "RHR" A valves overload alarm 903 two heaters found burnt !

8 06/07 1236 Started "B" RHR pump send water to radwaste 1240 Secured 1247 Started "0" RHR pump PASS Testing 1436 Secured 06/09 0925 "A" pump in torus cooling (for HPCI run) ,

06/10 0404 Secured 06/13- 0130 "A" RHR pump in service Chem Samp 0820 Secured 1605 "A" pump IN 06/15 0118 "A" pump IN 0825 "B" pump IN 06/16 0452 Secured 06/17 1657 Secured'"C" RHR pump

'06/19 1335 Started A Loop RHR in Torus cooling mode with A pump.

PASS vivs 71,72,65,66 open for PASS test.

2210 Removed A pump from Torus cooling 1301 Exceeded 1998 06/23 1900 Completed 8,5.2.3 (to inop Core Spray) 4-

--___-_2___________________

, l 106/24 0003' While'pefforming 8.5.2'1, FI-1040-IA and FR 1040-7 did not-respond, F&M submitted UE-MR issued. Commenced 8.5.2.5 for LPCI.- ,

1 0320 Signed off MR 85-424 for A RHR loop inop 8.5.2.1 completed , A-0325 Declared A loop operable

~

"06/26.- 0130 Tagged out loop fill for A; core spray 406/27 0001 Started C RHR pump and put A loop into Torus cooling 0838 Secured C pump from cooling _

A 1300 .A pump to Torus 3 cooling for PASS sample 3 a

4 06/27 1649 Secured-A RHR pump from Torus cooling'and returned PASS valves to normal.

6/29' 1831 Both A&B recirc; jumped up in speed. 2034 MWT, 1045 PSIG no' "out of limit temperatures or pressure" observed. Recirc speeds reduced. power and pressure returned to normal. -r 06/30 0610 Placed "A" pump in Torus cooling i

16K Torus water to RH.

1220 1255 '"C" pump in Torus. cooling -

2225 "A"-RHR pump in Torus cooling 07/01- 0637 Secured "A" pump from Torus cooling 1301 . Exceeded 1998 C07/02 07/04 0550 Placed "A" RHR pump in Torus cooling 1404 Removed "A" pump from Torus cooling 07/05 1140 Exceeded 1998 07/06 6700 Exceeded 1998

-07/07 2000 8.5.2.3 .!

07/08 2013 Exceeded 1998 07/09 2001 Exceeded 1998 07/10 0202 Exceeded 1998 0920 Power spike to 2014 MWT reduced speed of Recirc pump {

l 07/11 0545 Started A RHR pump in torus cooling

]

i 07/12 0254 Took C RHR pump out of Torus cooling 1 07/17 2300 Exceeded 1998 .

I :07/15 0025 8.5.2.3A 0305 8.5.2.1A R 2001 Exceeded 1998 l 2105 Exceeded 1998 l

1

, \

U ,

)

i' ,

1 i

07/17 -0020 8.1.1.20A (RX water level pertubation) ~

0846 Placed A pump to Torus cooling for PASS sample )

1441 Secured "A" pump i 1615 Exceeded 1998

] l

.07/18 0244 "A" RHR pump in Torus cooling i 1101 Secured "A" pump .

4 07/20 0530 8.9.10 (one diesel out) 0703 8.M.2-2.1.8 07/21 1023 "A" pump to Torus cooling 1025 Oper 16 1040 Removed "A" pump from Torus cool 07/22 0510 8.5.2.1, 8.5.2.3 0620 HPCI inop i 0816 "B" RHR pump to Torus cooling for I&C 1 0818 Secured'"B" pump from cooling 1039 Started and secured A,8,C,0 pumps (and A,8 core spray) for I&C surveillance.

{

'07/23 1145 Experienced an increase in flow on both Recirc pump . l loops. Reactor pressure approx 1042 and the bypass valves opened.

07/24 0335 8.5.2.1 -

a 07/25 0006 Put "A" RHR pump in Torus cooling for Chem Lab 0950 Removed "A" pump 07/26 1926 8.5.2.3 2035 8.5.3.3 ,

07/27. 0103 "C" pump to torus cooling 0630 Removed "C" pump 1350 Starting "A" RHR pump for Torus cooling and "B" RBCCW pump 2159 Secured "A" recirc pump-started on Oper 5 Sec D 07/29 0014 "C" pump to Torus cool 0124 14.7K gal Torus water to R/W 0532 Secured "C" RHR pump 1320 8.5.2.3 07/29 1750 Completed 8.5.2.1 2346 "A" pump to Torus cooling 08/01 0843 Removed "A" RHR from Torus cooling 08/04 1802 Exceeded 1998 1820 8.5.3.2 on "B" loop to inop "A" cont cool 2100 8.5.3.1 on "B" loop l

1

u 4;. \.y

?>

]'

Q e , ,

, ; p. . ,

Running'"B"&"D"JRHR;to'inop;"A" cont cooling tj .08/05: ~0003 -

'4 0030l 0031

L Compl eted' 8. 5;2.'1 Exceeded 1998.

y "

1 [4 -

q

'0515 ,8.5.3.7 "O

{

t' , J0530 "A". loop inop:

08/06' ,-0200 ' 8. 5. 2 .1 <

[08/07- 0245I : 8 ~. 5. 2.1 ? . .

NT-0940: :8'.5.'3.3 for MO-1001-26AL

'08/08: 8.5.2.'1L ' "

l0230

'030u 8.5'.3.3- n1 o/ 7

, p ' 'pt . , 4 ~, .

i08/08< 2046. . 8.5 3.'3 "A'! operable M >

8.5.2.1 "A" operable g#~ < ,

l08/11 :1905'

. -8'.5'.3.3 2008 8.5.1.1" l d( di ;)

'08/12' 0139- 78.5.2.1:

ik I- ([*.

08/13 2048 8.5.3.7.(equip inop). .,

.2117 . Secured 8.5.3.7 :(equip now op)

. 't 08/15- 0100 :"A" pumpLto: Torus cooling r ,

~'

0844 Secured pump- .ff/ 3 .

w<'

U.

2200 8,5.'2.1 " "g r G08/18 2230 -8,5.3.3'

- 08/19 '0115 All surveillance comp 1'te e for making "A" LPCI inop 0530. Tagged out MO-1001-28A c 2034 8.5.2.1 i e 2209 8.5.3.3 a

~08/20 0100' 8.5.1.3 "A" LPCI inop .j 2100 8.5.3.3 !

2102 8.5.2.1 i

08/21 0100~ 8.5.1.3 "A" LPCI inop ~j. f- -

8.5.2.1 2250

,i'

~

08/22 0050 8.5'.3.3 , ' , 4 Y.p3

-0100 8.5.1.3 9 14,:

08'/22. 0105 "C'.' RHR 'to Torus for Chem Lab h

-0225 Tagged MO-iO01-16A for, Equal

j. 1210 Removed "C" from Toruff, cooling -

-1230 Removed Temp Mod 85-36 ?? ,,

1420' Installed Temp Mod 85-39 ?? (, j 2122 Completed 8.5.3.3- ,. l 2142 Completed 8.5.2.1' I o j 1

- )

c_ . , . ~ ,

y - -

37; f 1 ,

?

lQ0 f.

rp:-

( 1':

jn .. . .

. . .. . if J08/23i :0342': <

tSurv'for'LPCI complete ..

- ., 2127' -8.5.33

2157 L8.5.21 7

108/24 i f 135-0 :LPCI' complete:

1700- '8.5.2.1

% :1729; LPCI operable.

-22511 ;Surv-to inop Core Spray. completed- -

m

!ff :08/25: 0930 - 8. 5. 2. 3.'

.1130- 8.5.2.1 C,, f T '

' y c

'08/26 0929' 8.5.2.3 "

-1000 - 9K from.Torussto RW (unknown pump)-

11191 8.5.2.1' 1155 Power excursionLfrom "A" Rectre Loop. Y, .

e x E08/27 0453' 8.5.2.3 1-1030' 8.5.2.1- "

rg "2101- Exceeded 1998

[ -

u

! p /Y;:

L08/28 0034' 8.5.2.3.

M 1048 -8.5.3.3 -

f 1121' "A" pump to Torus cool >

1136 ." 8" pump to Torus cool /

.. 1344 8.5.2 1-.

1530: 14,500 Torus-to R/W & -

1950' Secure'd "A"-RHR pump, Chsm lab got sample

~ 08/29- .0527; . 8.5.2.3 '

0528 8.5.3.3. c//. ' .s g

'1307 8.5.2.1 i

~,

i 08/30 0540- 8.5.2.3 ;

0600 8.5.3.3 '

1358 8.5.2.1 s'

~

'08/31

\'

0503 8.5.3.3 .

0530 8.5.2.3 L1332 8.5.2.1

'09/01 0520- 'RX Scram (yard washdown) 2000 "A" pump to S/D cooling IO9/03 0415 "B" pump to Torus cool ys 1211 Removed "B" from Torus crid{

'09/04 0140 2.1.78 (operability of 1001-68 A/B) "

09/05 31250 "A" pump in S/D cooling 3 ,

09/06 0148 Credit taken for previous 8.5.3.3 & 8.5.2.3 r 0250 Secured RHR from S/0 09/07 1243 Unit. on line I 1, _g.

I

-:: P'

V' %4 ]) t , [I u

), s ,

.f.

n n 9 30 "B" puopt to Tcrus cool i"yU 3 09/04 hi 7 RHCE p1obiems:(started approximately 1545)

~

0 8.5.2.3' 'l

[9^/79t. J230 , 1 22 ; l0 3.5.3.3 l

a o s s+

07/12 'd530 "A" pumo +6 Tet i n cooling r-0703 , Exceede:' i998

?I54' y, 9700 gal from Torus to RH 1512 i Removed "A" pump from Torus cool 09/13 0010 "C" pump to Torus cooling, 4500 gal to R/W

\ .J 09/14 0805 "A" loop to' Torus cool for PASS testing 1348 Secured ~orus cooling

- 09/i5' 2030 8.5.3.3

'/* O'9 /1'./ 0245 Compieted,8.A.16 0545 LPCI system ir,op MR 84-10-254 1856 8.5.3.3 2056 8.5.2.1 09/17 0130 8.7!1.20 RF Puturbation 0235 8.h?.5 LPLI inop .,

1709 Te%p Mod <85-46 MR 85-572 '

1725 8 . l l. 3. 3 '

$ 1807 8.5.2.1 <

j 09/18 0210 Temp Mod 84-46 Mo-1001-288 0 Ring replaced by packing i

, 0215 8..i.2.5 i 1530 "A"" pump to torus coo? for PASS sample ,

i 1540 Secured l 1902 8 . 5 '. 3 . 3 l

1253 8.5.2.1 ,

Osfl9 0130 8.5.2.5 0735 10.5K gal to RW from Torus 0850 Problems 1001-29B 1435 Started "A" pump to torus for PASS l 1556 Secured "A" pump 8.5.3.3 1829 1 2035 8.5.2.1 09/20 2110 8.5.2.1 09/21 1716 M0 28B & 298 operable 09/22 2203 8.5.2.5 8.5.2.1 8.5.3.3

'l t ,

b 09/23 0100 8.5.2.1-

"A" LPCI'inop-

~

0540 17201 : 8. 5.1.1 '

1800- 8.5.2.1, xy 1830' 8.5.3.3:

'1845- 8.5.1.3 1925. 8.5.3.1-2010' 8.5.3.2 c09/24 1700). Survs for LPCI inop.

09/25" 0225- 8.5.2.3 2000 .Survs-for LPCI~inop

'f09/26. 0406' "B" pump 11n Torus cool for Chem Lab (Hurricane Gloria) 1331' B" RHR secured from Torus

, .1540- LPCI declared operable ,

09/27 1620- "A" RHR to Torus cooling 2015 Secured "A" pump 09/30 13151 8.5.3.3- l 1320 8.5.2.3 .

0900- .RIT-1001-606A inop 1700 Exceeded 1998, took corrective action 10/03 0015 "A" pump lto Torus cooling .

0900 ~ Secured from Torus cooling. ;

10/04 :1438 RIT-1001-606A operable (MR 85-596) 10/06_ -0142 8.5.2.3 0417 8.5.2.1 ,

0418 8.5.3.3 '

1501' Exceeded'1998 l

1818- 8.5.2.3 !

1841 8.5.3.3 1947 8.5.7.1 j

i 10/07 0505 Exceeded 1998 10/08 0254 Surveillance for Containment Cooling EQ (36 & 37 B)

'0255 Cont cool inop 1027 10K from Torus to RW. Put "A" pump to Torus cooling 1838 Secured from Torus cooling

-1845- Survs for containment cooling eq 2030 Tagged out M0-1001-10B for Equal 10/09 -1700 8.5.3.3 MO-1001-37B 1815 8,5.3.2 "B" loop inop !

1915 TP 84-309 "B" loop inop 2030 8.5.3.1 l 2045 8.5.2.1

'i

3 l10/10f 0013 "A" pump to Torusffor Chem Lab .,-

- 1829 Secured '.'A" pump 1845- Survs. for' B" loop out 10/11- - 0702. Exceeded.1998-1800- Survs.for "B" loop inop .

10/12' - 0350 8.5.3.3 forJ.1001-34B 0539 "B'. subsystem operable

'10/14 1941 8.5.3.3 (LPCI;inop) 1910: 8.5.2.1 1 1908 -TP-84-309 2340 -Completed 8.9.1 inop LPCIL 10/15 0600 LPCI inop A

0745 Per CUE, "B" LPCI not inop, "B" cont cooling inop-8.5.2.1-for "B" cont cooling.inop

. 0830

. 1633- ,

8.5.3.2 M0-1001-168-1651 TP-84-309'M0-1001-16B i cm 1804 8.5.3.3

'8.5.2.1 1806 .

10/16- 1942 TP 84-309, 8.5.32 M0-1001-16B 2313' '"B" cont cool; subsystem operable

~

10/17 0200- 8.5.3.3 to inop "A" cont cool. !

% 0449 TP-84-309 0505 8.5.2.1 .

.0550 "B" pump in= Torus Chem sample-1400- Secured from Torus Cool, 1415 M0-1001-34A, 37A closed-ineo 2047 8.5.3.3 J 2048 8.5.2.1 .!

2049 TP-34-309 l 2230 EQ on MO-1001-37A finished

-l

'10/18 ' 1400 "A" subsystem return to service

.f 1608 8.M.2-2.1.7 1

-2.1.3 J

-2.1.8 1631 8.M 2-2.1.9

'10/19 1815 "A" pump Torus water to RW 1819 Secured "A" pump 10/21 2100 Exceeded 1998

.10/24 0015 "A" pump to Torus cool l 0815 Secured Torus cooling '

10/25' 0300 8.5.2.3.1 l

10/27 0830- "A" Pump Torus water to RH 0837 Secured "A" RHR pump -

10/28 0445 8.5.2.1 (Core Spray inop) 10/29 1312 Exceeded 1998 10/31 0005 "C" RHR for Torus cooling 0820 Secured Torus cooling 2225 ... reduced Recirc's to min speed 11/03 2129 8.5.3.3 8.5.2.1 11/04 0442 Completed 8 5.2.5 "A" loop inop 1200 LPCI inop for EQ 11/d4 2230 While performing 8.5.2.1, MO-1001-36A would not open -

unusual event 11/05 0815 36A operable 0830 broken wire pn1 904 "B" recirc MG set speed 1610 Observed RR-1001-606A and RIT-1001-606A on Pam Panel C-170 cycling on a periodic basis 2110 8.5.2.1 11/06 0522 QC hold /NCR tag placed on C/S for "A" RHR pump 8.5.2.1

~

1840

, 1908 Completed MR 85-10-73 on "A" RHR pump-operable 1910 Tagged out "C" RHR pump for maint 2048 8.5.3.3 11/07 0401 M0-1001-28A operable (MR 85-10-76) 0957 8.5.2.3 1506 LPCI operable 2030 Completed MR's on "C" RHR pump-operable 11/07 2035 Survs to make LPCI inop 11/08 0110 "B" pump out for EQ 1455 Clearing MR on "B" RHR pump (due to Op5) 1715 Completed MR 85-10-72 for "B" pump - declared operable 1720 8.5.2.1, 8.5.2.3 LPCI operable 1722 "D" pump inop surv (credit taken) 1725 Tagged out "D" pump 1/50 Secured Oper 5 11/09 0921 8.5.2.1 "D" operable 11/11 2016 8.5.2.3 2046 8.5.3.3 2250 8.5.2.1, 8.5.2.2

't k'

'11/12- 0600- Tagged M0-1001-34B for. Equal

~

L1253- Exceeded 1998-1805 '8.5.3.3 2148 8.5.2.1 l11/13 '0330 .8.5.3.3 for 34B 1023. ."B" cont cool operable

'2200 8'5.2.1

-2219 -8.5.3.3-11/14' 0130 TP-84-309 "A" cont cool'inop 0230 "B" to Torus cool for Chem Lab..

.0900 "A" cont cool.inop

'1147- Secured "B" from Torus cool 2124 8.5.2.1 2140 8.5.3.3 2337' M0-1001-34 EQ complete operable l1/15 0000 Exceeded 1998 11/19. 0924 8.M.2-2.1.8, 8.M.2-2.1.9 !

11/20- 2324 "B" pump to Torus cooling 11/21' 0301 Exceeded 1998 1 0501 Exceeded 1998 - !

0550 Dropped 6480 gal Torus to R/W ,

0830 -Secured "B" pump '

11/22 1520 7000 gal from Torus to R/W 2354 Put "A" RHR pump in Torus cooling-Torus bulk temp.@ 77" 11/23 0435 Removed "A" RHR pump from Torus cool 11/24 2330 8.5.3.2 11/25 0340 8.5.2.1 i 11/26 2001- Exceeded 1998 11/28 0035 Put "A" RHR pump in Torus cooling for Chem Lab 0715 Dropping Torus water to RW 845 "A" RHR out of Torus cooling 11/29 1617 Completed 8.M.2-2.10.2.8 3 12/04 2003 Exceeded 1998 12/05 0022 Placed "C" pump in Torus cooling for Chem Lab 3

0837 "C" pump out of cooling i 0900 Exceeded 1998 '

1800 Exceeded 1998 12/06 0180 8.5.2.3 1

.__-__m_ . _ . _ . - . _ _

~

12/07 0801 Exceeded 1998 -

12/11 0040 Started A/C RHR 0050 Started B/D RHR 0100 Completed 8.5.2.3 0130 Completed 8.5.2.1 12/12 0002 Started "A" RHR to Torus cool for Chem Lab 0900 Secured Torus cool 0501 8.M.2-1.5.5.1 (RHR Iso vivs) 12/12 1945 8.5.3.3 1 1948 8.5.2.1 2000 8.5.2.3 12/1.3 1202 Exceeded 1998 12/16 2030 8.M.2-1.5.4 (

12/18 0016 "A" loop in Torus cooling 12/25 2345 "A" RHR pump to Torus cool ,

12/26 0830 Secured from torus cool 12/30 0745 8.M.2-2.10.8.2 .

8.M.2-2.10.8.1 S

l 1

1 A ee o o dir T3 O

~

I l

l l

t, i Av k

.~

1 1

0

E p- . .

'oEEENDIX E l -

EDSSIBLE'SOUBCES DE BIOS EBESSUBE ELVID LEsto0E INIO BBB PART'ONE - Source of Inleakage

. i

1. What ere the sources of.HP fluid (OT 400 psig) at PNPS?

React'cr vessel -1000 psig

.RHR. Core Spray pumps (at shutoff)

'SBLC-(1100 psig when tested)

RUCU -at Rx. pressure n'"

HPCI. RCIC at test Main steam Recirc Feedwater Condensate Transfer

2. .Which~of the above sources tie into RHR7-

.Rx vessel RHR. Core Spray test line HPCI

.RCIC (min. flow) -

RWCU

~? Recirc.-RHR injection lines. enter a recire pump discharge'

-RHR Pump. discharge-Fuel pool inter-tie ,

3. Where do the above sources tie into RHR?

.i !

Rx vessel - at injection pointi shutdown cooling suction Recire. - at injection point Core spray .into Torus cooling test line inboar d of 1001-36' s Check v1v HPCI -1&nto Torus test line inboar d of 1001-36's Checi viv RCIC - into Torus test line inboard of 1001-36's Chec k v1v RHR - 15 the system itself - and shutdown cooling RWCU - branch off of shutdown cooling line. No other inter-t t e F.P. cooling - branch of f of cross connect l

1 4

1 1

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e

_ - - - _ _ _ . i

g 1 *s pf L

{l

-X '

s .

l' ' f. ..

.I / APPENDIX.B-(continued) Page 2 i

^

n 4. j0f.theJabove sources. state reason.for., elimination:

[ CORE SPRAY,- Normal' core spray test pressureLis 253'psig'.'.PumpsSdo not approach shutoff. head: therefore.' a source of pressur e Greater:than 400.psig.is not provided. Also, this source

- t ies- into RHR insi de of M01001-36A and B. in ' or der.' to-pressurize.the RHR system. Two (2) normally-closed valves would have to leak thru rather than have this source go in.

the unobstructed path'io. the Torus.

RHR PUMPS - 'N'ormal system test pressure is 172-psig: pumps are.not' commonly run near shutof f conditions. When system is run.

the flow' path provided relieves pressure in 'the system:

.therefore, the alarm does not annunicate.

-l HPCI RCIC - Minimum flow 1'ines tie into RHR at same point as Core. -

1 Spray. This' source is eliminated for the same' reason.

Also. there is no correlation with ECCS surveillance L testing with the frequency of occurrence of RHR pressurization alarms. -

_ :&}

~

A.9 RUCU - The only inter-connection is the commen suction off the Recirc: loop with.the-shutdown cooling suction line.

CONDEN? ATE TRANSFER - Ties into RHR for-the keeptill system outbcar4 of the RHR pump discharge. The maximum condensate transfer pressure is 100 psig.

i t

FUEL POOL INTEPTIE - This source joins at the er oss t ie but is isolated by 2 manually-operated and closed valves and a spectacle flange. System pressure is nor mall >

225 ft (approx. 100 psig). This path is not a likely source.

i i

l 9

(

' APPENDIX B.(continued)' '

LPage 3

5. What' sources. remain possible causes for Inleakage?' l Reactor - Shut down cooling suction.

Reactor /Recirc ; discharge - LPCI injection point. A & B Loop.

.6. What evidence'is available to prove or dispr.ove the. sources of.-Item.5? i REACTOR SHUTDOWN COOLING SUCTION:

The leakage mus't propagate thru the' following boundaries - M01001-50. M01001-47, any of 4 M01001-43 A.'E.

Ci D system.- Pressure beyond the. 1001-43-. valves'is 110 psig at the l pump discharge check valvesi 6 psig in the Torus. The path of least resistance'is through the normally open 1901-7A. B. C or D valves te the Torus. Additionally, when the RHR high pressure alarm annunciatesi-the pressure is relieved through the Torus cooling line: if the shutdown cooling suction path were the pressure source (meaning PS1001-82 was the device tripping the alarm) the r elie. ing ef for t s woul d have no ef fect.

d REACTOR / RECIRCULATION PUMP DISCHARGE:- This source would propagate -

through the- 1001-60A or B check valve, the M010C1-29A or P gate valve (if closed), and the M01001-28A or B globe valve (if closed).- Only~one I of the motor operators is normally closed. .The pressure. switch tc.

alarm would be either 1001-74A or B. Since the RHR. loop cross tie is "

, nor ma11/ openi the whole RHR system is essentially .open to:pressuri-3 'zation. Either. or' both injection paths could be the source. When'the pressurization problem was initially brought to light. (in January 1986), walk downs of both loops were made. The walldown found the "A" ;

RHR valve room at normal, ambient ' temperature along with the shutdown. l cooling line. The walkdown found the "B" RHR valve room extremely hot with pipe temperatures at the level of pain when touched. .This observation allows the conclusion' that RHR. system pressur i:at i on was caused by leakage through the "E" System.

i l

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1

.PNPS FAILURI AND MALFUNCTION REPORT

)

1 )

$* _. & '..3 Pam No.86-036. EwNTeast 3-/f E ' EVENT Tat /A6d

.- .- )

EVtNT - (OR 6INATOR)

' *' . A. tytNT DESCRIPTION: -

I '

Activity in Progress 1.

4gS ,

, 2. Circumstances Leading to Shet sweet' v/ .*5dede

^/ ~ ,

Nuvr O' nerediore nd MU R wer'

' l

3. Event Description #ee n rad a ~ #NX m.vA2,ce /w,6h /L/ um N i

{'

Pro *.Aurn Aunwe;Mu M sA v2 /vwE <heheM uslue a Mn DHA sm on ti 3r d / mig '

~

4. Probable Cause VMvs MO -S F R la p Ki na b v.

Reported by A t ::a n k'. 6 h ir ve r ' '

DAIL S- @b '

E,7 l CORR VE ACTION INiilATim - (tenTCN tm61NCER RivitW)

- ~

- a* A. 2 (N) Event is Safety teleted j

l .

(N) Event is Tech. Spec. Related System No. '

?. N) Tech. Spec. Action Statement tatered J

8. tLCTIVE ACTION INITIATED rr"_ ram 4 /)./Tech. #4 Spec. Section. m . r R X .

m/At,,r l ~2h*9Y M, Jns m ,c

-.e ,

, . -rd . .y - (N) Maintenance Request Issued

3 V (N) Procedure Ut111204 M.R. Number K/2 ** N K . [

C.

Proc . Z-. / j i

(Te sitigate effects of failure)

COMP T

g'l-3enA 4

"* i D. N011tlCA110N5 Telephone itse !

aA 1 red (.r.fittig actification Time Limit Nottf1 d Person Coc.f.uted.

(Refer 2.2.17) Nuc. Ops. MRr. 24hr. Abr. Ihr g -

4 (Refer 2.2.11) NRC (via ENS 24hr, 4hr. Ihr ,,,,,e,

.% (Refer 2.2.11) Less C P

~-% gr

,1. . _ . _. : , , , I .

WATCM EN6tNIER,516MATURI __

_u

, ?? r'?.4 "> '. IVENT REVItW - (5MIFT TECHNICAL ADVISOR REVIEW)

A. PLANT STATUS JUST PRIOR TO EVENT

1. de (N) Am. Critical 2. As. Pressure lo O 3. Rs. Coolant Temp. r a *r

4. As Mode SW #uu 5. As. Pwr tv1 . /e ek

t. j' APPLICABLE PLANT (GUIPulNT STATUS 1 Redundant safety systems available and operable are Me / **/ - it s /.._=-, J %

2. Safety systees not operable erst in /ea r . na

3. Major congern Ms /se/-at A n uen A m r ha. . ma -

b A

f, WA 1ho u . e .sa nk r,n -rt e L.a u Aue wa ' na a m'. no m in s,p fluer u o n )

eLauna /M u si.ueu C. SAFt1T A5]ESSMENT ;

1. (V) Ol) Constitutes an accident er malfunction of a different type than evaluated

. . previously in the FSAR.

(f)

. .. - - - - - - - Reduces the margin safety as defined in the basis of Tech. Spec.

(Y) Increases probab 11 f occurrence or consequence of an accident, answer is

74. ,

n6 if act1 ired Toetn soot. is taken.

STA SIGNATutt _

'h DAf t ,r/fp/ W, RIPOR11 (COMPLI ANCE Rivlt f) /

A. (Y) Licensee twent Ap)t. (LtR) Recommended Per 10 CFR 50.T3 Section/ : 40t RWhd k.

8. Basi for recommendation: 2A B (Mv la4 L na k m e m i A nH- ha u t occurserz8 . the, C.

kl diese M t PrT m iah b m lead Group Ass 1(ned; '

a'w,a i P r.th u r # A th un t H en t . 464. fm eqvg trwtw. V.A

COMPLI AEtt (NGINE(R 516MATURL M/h /a't.L i l- ~ 0 Alt :2J/'t /N 51A110N MANA6tR APPR0tAL l .<Mfm '

DAf( , f i'/ k /

b i' ' 'I '

O.

- %(V) Vea w tr/

g s% Significant (see Dt0AM.

. 11 a h Section e Low 16) n M tuplehnbe.s ~; et p .3.f.FG c,-r %q ,

ua.1 star 1rn.h. e rw ogh Fi*

0556P ttADLR 5NNA1URL -/ e( ///e<hes -- 04H A - -.

y r 0-ORC REY!IW -

ORC MitTING NO. DATE 015P0511!0N -

Method COM 41ANCE EA00P tla0(R SIGNATURL CAtt CLO$t-0UT -

AUTHORilt0 SY CAft r 1.3.24A-1 Rev.11 cedd shti Cfu i d't0 t @< ty>n} (c" w~' rx A v.s 3 m r s , ,

L a ..... .. ~

u a

L

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~

- REC'D MAR O' 61986-i j

STA OFFICE OFFICE MEMORANDUM l Boston Edison Company 986302947 l

l

- RNG Control Nun.ber

, 70: Mr. C.J. Mathis FROM: ,

DATE: March 4. 1986 DEPT. D00. STA86-026 Record Type Ad.00 I Non-Safety Related l

SUBJECT:

l EVALUATION OF F1H 86-036 - M01001-28B LEAKAGE

[{

Distribution:

J.A. Seery P.E. Hastrangele . ;

A.L. Oxsen M.N. Brosee

P.O. Smith R.E. Sherry STA Memobook {

1

____________________________________________________________________________ i I. SEVEB11Y_8SSESSMEUI The alarm "RHR Discharge / Shut down cooling suct ion high pressure" is ;

indicatives in this case. of leakage past the closed 1001-28D valve. Ducn-- i ti fication of actual. leakage cannot be per formed; however. it' is' judged to be less than the relief capacity of the downstream pressure relief valves PSV1001-228. PSV1001-228 has a setpoint (tested RF0115) of 428 psig and a capacity of 110 gpm. -

.}

In this cases the primary containment boundary is assured becauce the i isolation valve N01001-298 was operable and capable of closure. Alsoi over-pressurization protection is provided by operator action to relieve pressure when the alarm annunciated and by relief capacity of PSV1001-228. The pipe :

in cuestion, outboard of 1001-28B is 0 Class 09-10. design rating of 500 psig f 350*F. normal operation 256 psig 80 F. maximum 600 psig. 300 F (Ref M300).

In response to potential overprecsvrization concernsi the normally j closed position of M01001-28B and the normally open position of M01001-29B j were reversed. This change took effect on 2/26/06 at approximately 2020 l hrs. '

q II. SIGUIEICOU;E_QEIEBbIU6IIQU From the standpoint of a Significant Condition Adverse to Qualityi the event is not significant por present criteria. Since we are to change !

criteria to the NSAC/INPO criteric soon. this screening sheet ( dr a f t ) was -

used. Evaluation per the new criter ia classi fies this event as catesory N1 '

1 "A single failure occurs in a redundant system": there fore, not signi ficant . ' l III. JU1IlEIC61103 Other2 (non-BECo) have reviewed this event and have had cencerns, in light of both the containment iscletion issue an d the os er pressur iret ien ;

issue.

/ Fundamenta11v. this entire event reveals that check va l ve 1001-(.D 1 is not lealtight.

In the os. inion ci this evalustor a r. d < t n e r F M i W :'~7 %

reviewersi the 680 check vcive is not intended to be a leait y

}{c[f]'

1

'h .'

l fur 0 51933 I l

, eA. l

- _ _ _ - _ _ _ l

7

m. ,

_, ' Doc. STA86-026'

TO: . C.J. Mathis .

DATE: March de 1986 Page 2

SUBJECT:

EVALUATION OF FEM 86-036 - M01001-288 LEAKAGE

. . III.~ JUSIIEICBIIOS_iconilovedF Our Appendix J. submittals of the 1976-1977 era, requested exemptionitand NRC granted the exemption) fros local leak rate testing the 1001-603 (and ,-

68A) valve and to tesi'the 2001-29 and 1001-28 valves instead.

In a responce to violation 83-23-01. BECo stated lits position with "

respect to downstream piping overpressurization in the RHR system (and core-spray) in letter 84-130 as "The downstream piping in the low pressere ,

systems is protected by the closed valve in conjunction with a valve logic interlock that prevents simultaneous opening of both the 28 and 29 valve or

'the 24 and 25 valve above 400 psig reactor pressure. There is a piping high pressure alarm. outboard of M01001-28 to annunciate if the line exceeds 400.

psig.- Additionally, both systems have relief valves downstream of the motor-operated valves to mitigate downstream piping overpressurization within the capacity of the relief valve." ~

Based on the preceding statements, this reviewer concludes that the.-

subject event of F&M 86-036 is.not a Significant Condition Adverse to Quality. Corrective action of closing the'1001-298 valve is more than , !

,-s ' adequate in response to leakage past the 2001-288. The valve lineup has

. [ cr, been returned to its original design lin,eup. Operation in this. lineup

' s, s proves that containment integrity was not compromised. i.e.. M01001-298 does not leak and would have provi.ded a containment isolation if called upon. .

I V .' C6V2E A root cause of this event cannot be pcsitively declared. The absolute answer of the reason for 1001-280 leakage will probably not be identified until it is local leak rate tected in RF0 7. There are some facts that aho

recorded here as possible contributors to cause.

1. Local leak rate history of 2001-282:

1960 - As found .1 SLN. As lef t .2 SLM 1982 - As found .5 SLN. As left .5 SLM 1984 - As found 1.9 SLN. As lef t 1.9 SLM A predicted "as found" leakage of 1001-280 has been modo 3raphically at 4.75 SLN assuming an exponential rise: single penetration leakage limit is 7.89 SLM. The prediction graph is -

attached.

2. As seen above. LLRT history o f M01001-280 is good. There have been '

no failures to date.

)

l l

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c___--__-___- _ i

(i E' 4 < 2

\

m a m: . . . _

^ r. ,

?: */ ..

6 Doc. STA86-026 270:' C.J. Mathisi iDate: ' March 4,71986 Page!3

SUBJECT:

/ EVALUATION OF~ FEM'86-036 - H01001-288' LEAKAGE ,

,~ IV.. C6USE.lgebiloug41 '

3. - There. are no: reports of;28B valve suspect:1eakage prior to January ..

1

.ld;; 1986.1 A contributing factor may have been the draining of; the. 'B':

RHR injection 1ine to repair the-1" pipe-leak' inboard ofi 1C01-66B d during-the January 4 shutdown.. 1 q

U 4. Initial findings by Electrical- Maintenance revealed that clostra b} amperages on'the valve were not' repeatable initially. This led to

[ .

the disassembly of th,e valve operator ~ No abnormalities were- .

1: ~. f ou n d . Upon reassembly. the valve closed consistently with 200:to

-108 amps.

1:

. 5.- A similar leakage problem is not evident in the A loop of RHR. .

i.

. Based on the above'information. a root cause is speculated t'o be' incomplete

~

seating of-the valves caused by foreign material or' wear.

1 , .

..v. BECQBdEUQ8Il083

=

I 1. ' Realign the A loop RHR to be-i'dentical'to B loop. This-is y suggested to eliminate confusion for operation and lineu:.. ,

_q-

}

A 2. At the next cold shut downs provide shutdown cooling . flow through '

q. the B loop. This may' flush the valve seat and may reseet the injection !

j' check valve. A test could be performed af ter shutdown and ct resctor

l pressure to assess leakage through 1001-288 by- temporarily reversing valve j j' positions.

, j

-'l 3. !

Prepare for preventative maintenance to valve 1001-23B pending j

'n local leak rate test results in RF0 7.

g 4. . In light of thio event and the NRC-I&E involvement > consider re:ent l NRC-flRR concerns regar ding Pressure Isolation Valve (PIV) test:ng. but negotiate acceptance criteria to a pract: cal level. This testing weuld b'e

.per forme d at func t ional differential pressure across the valve. There w111 l be procedural and budget impacts associated with this recommendation. A possible. outcome; however. of the present IST Program review will be a h requirement to per form PIV test ing. p I

t SSU:1f '

Attachment l a

,* \

i f

l l,

_____l_ ._1.__ _ . ._ _ l

1

-f if ' .

PNPS FAILURE AND MALFUNCTION REPORT

'q r ga. .

-N * >h

, FM NO. Wo-oet! EVENT DATE / 'd EVE *fT TIME /f/[

A. EVENT DESCRIPTION (FM ORIGINATOR):

j ' -

1. Activity in Progress her 4' 93% Skede 8///b/#c

2. Circumstances Leading to Event P.,,,,ot b'/pd rurt _e / u aw, r , A O

N 3.

.w k h ; s ers wa a= o* u n caA> m "/w/PL _n vem fo%'s A dm a ht e%is

. ;f. ' Event Descrip% A %,% /UAmt i on tCnL * ## wu N "Nux/s W*' #(ke *"* w ""*T F' ' W'"* -

R, c.aed o' 4 uae

' k T u pa n r. I 903 -L Le -272 ' A/t0E a'eefoe,J & (,i e orp 2 9p rae os et '-!=. B L ocr LA r

~\ ^

4. Probable Cause vrtVe ne# fut*< e. >/ m Mir -

M Reported by m Al 9f M " '/ssdM-A ~-- DATE

' - Wo/It'

/(

B. CDR VE ACTION INITIATION - (WATCH ENGINEER REVIEW)

- 1. (N) Event is Safety Related (N) Event is Tech. Spec. Related System No /0 .

(N) Tech. Spec. Action Stat,epent Entered Tech. Spe:. {ection/ 4 I# 5 .

2. ORRE V ACTIpN INITIATED c 'e=> - - - #' _f"J .t (4 /er . /-o ) ~'

l f/ re - f o o l .298 . hin t M . '.o -A ,

l h(Y) Maintenance Request Issued Procedure Utilized M.R. Numb 1r 64 "/O -/4/ l Procedure Number - l

3. LCO PENSATORY ACTION (To mitigate effects of failure) l l

4. NOTIFICATIONS Telephone Time Reauired Criteria Notification Time Limit Notified Person Contacted

! a) (Y) (Refer 2.2.17) Muc. . r. 24hr, 4hr, Ihr b) (Y) (Refer 2.2.17) NRC via E 24h , 4hr, Ihr

c) (Y) (Refer 2.2.17) C d AP WATC NGINEER $16 NATURE w, .s/--- _

\ C. EVENT REVIEW - (SHIFT TECHNICAL ADVISOR REVIEW)

1. PLA TATUS JUST PRIOR TO EVENT -

a) (N) Rx. Critical b) Rx. Pressure /# /3 c) Rx Coolant Temp. Vfd '/-

d) Rx. Mode SW /C tr 4 e) Rx. Pwr Lvl U <A.

2. APPLICABLE PLANT EQUIPNENT STATUS f , jfr a) Redundant safety systems available and operable are*

b) Safety systems not operable are: #M 's , c, 4 /G^ /pe r '

dm c) Najor concern snr tret-x s L l.1 4. J nh'- -4 J a.e4&~u 4 6 nuuw. OW.m. / % d m ole:;=. WA. 'in e' sen t - 2c n n._/

rn c scet.Y o rg stauf A " , L t,J o ' & K cm A-- ~ wu

3. SAFETY ASS SNENT ' / '

a) (Y) ( Constitutes an accident or malfunction of a dif ferent type than evaluated previously in the FSAR.

b) (Y) Reduces the margin of safety as defined in the basis of Tech. Spec.

c) (Y) Increases probability of occurrence or consequence of an accident, answer is no if action required by Tech. Spec. is taken.

4. SAFET SIGNIFICANCE (Fill out a copy of Attach. D. Proc. '.3.24) Pr e U A v'/n /f 4

). REPO G - (COMPLIANCE REYlEW)

1. (N) Licensee Event Rpt. (LER) Reconrnended Per 10 CFR 50.73 Section: Gdr i) i

2. s for recommendation: L Pe r i.s cmsikstr/& situ /t tram '*'svue m and k l fr Mr h I,/t FLA* "

6"D.13

3. (( JV (N) Root'cause analysis and corrective action plan required?

Tasis: /'es/w M o s / Ez' cA L M -/o If yes, Aftach. 8, Proc 1.3.'24, or equiv., shall be completed Lead Investigator GrMA/ (bottmrtA/ Lead Group ENr v/7Lis Tram

4. (N) ORC Review Required?

5. en 'Sionifica ' notifv VP-N : Person rd v%4 of tu nwr nLA c ntnnte ntacted cALgg,.goA L O/J44 Date 4/r3/$fa '

PLANTENGINEER$1GNATURE/7) __

DATE 4//C/ft, STATION MANAGER APPROVAL *' DATE '

K . ORC REvlEW - (If required)

ORC NEETING NO. DATE

. DISPOSITION -

Method l COMPLIANCE GROUP LEADER SIGNATURE DATE 4 . CLOSE-0UT -

AUTHORIZED BY DATE 1.3.24A-1 Rev.12 l

l

'i' F&M No. 86 ~$4 Date '/ htl B (o

( /

~F&M R001 CAUSE AND CORRECTIVE ACTION PLAN-

1. - LVerified event ~ description. Synopsis: Keec+ luthy pa SY N /dd/-29R ' l

(s jtessurogwy' ftJD*9 M nsfr w & /ko foot-zgg, . ^

ThlA & 44 sead far- 4-o eceuro u <

W +%.~ mot 00/-20y & tG i occamnce. Pi

%(~-efNseyNfmf~8 st & M 66 3f ;

& M-fa4

/b $ e9")n%&4{cL 3 50*F82 W O/* f'f

?' - p &Sm h fue. g of. z e g a V (ce V-t-t 9

\

.}4x4 4 S-*4-f et i .6 ysig 4kAt b O /tre /to yf** A

5 fd k 9eo t2

.2.~ Most probable cause: A Loh It M4 -

l 1

~

4 i

\

'i JC .l. p ' Actions Completed / Planned (include dates):

%TWJ6 MTH '2 9 f3 T.VVT' - $f 4 fA "b b A UA * -

\

CoMq 'j rJ SvGUQv&MLf (dITHM) 60'Tb Cold $~N E0W U ,

i i

4. Recommended Actions to further determine most probable cause/or !

preclude recurrence:

Ov{n ),Mv L VA w G -- AWhy 26 GVSC ,

1 i

. Completed by:

Agreed to:

Lead Investigat Lead Group, Group Yeader b Date 4 "//- /6 or Chief Oate l 1.3.248-1 Rev.12 l

h.

a l

M j ATTACHMENT D kk .

- l

'} -

INPO SIGNIFICANT SCREENING CRITERIA i,

sam frac w r mone:nonau.v saamankesrr ser stunneeser

_ 51. Two or eere felleros mesur _ C1. A eingle fellere soeurs &a _ W3. A namele feindre esswre to redendent erstene during a mes*redundsat eyesen. &a e redendent eyes o.

* " "**** e Sees the fellere vioasta 53. Beer-eritisit degradation

_ st. gwe er more failures due se primary, seeendary, or of.tmoundaries eseur treae-e temmuon eeuse eseur Gerleg sentoaaneet prosaure bound. Aug toe e. seen leone, .

the some evoet. ary. . emho asehe, etc.).

"""" sl. Three er oore felleres sesor e pese De fa11sts lead to a """

83. Personnel errore end pre.

dorlog Oe same event. mejor plant tronatomt le.g., emdatal deficiencies are i St. Component failures eseur II I"*8 *I ***8 **' * ** **' '

.ootso u me.e..any ~wa.**'*"aca*'.. sa i - , g: "a*J;a-~2 g';gIS'"# 8

< eeceped detettien by testies '""" c3. Two apperently mateleted or esenAmetten. felleree eseur daring the ,,,,,,,,

W 4. SeJamie deficJessies eerwr S t. An event preseede an a way

- ""**** IP88* N*t*'*. eaubtere. -

significantly different fsen e Are the fallares commen S ****3*

abet seend be sap eted. eewee er madet , _

WS. Campamente operate set of

-auau ~ < a -as

u. .e e.e.t - e,e eues ee.u. e 1

- u d ,.

- - one .e fan of .eese u.t , .e.

,. u se -m.e, m on.eio,ed mt ,uhat

.et.e.19e sanoel g m .,n;e,ga, m g ;;;:

,eo.,e, e s. ,

i bases * ,,,,,,,C3. A prehles ree.vnt.e la.ee ee '

.'eff* - 96, pan-v.adu,s.gisetto,e eses,varm.

n . . ,e ,u ,,le, o,,,,,e.,e ,, she enau. r ie o,e .

Ug"ddt"ob d 4 ,eu. o I's",*~2'""Luus.. 'a ab <-na-seveve11y M ght _ J. Donegraded from tends-e Die the role ee er espeente I*** U I 888"A U *****

eerar mader ensemaa eiseen.

st. henanistrative, procedural er *******I '

operetienen errore age amm. *"""" C4. & desige er menefattaring ,

i matted that resulted from o defieleney le idenuf ted as l g fondementel nieunderosanding the sepe of a fe11ere or - , l i of plant performance et potenu el fallare. , , ,

m fety requirements

e le the deficioney na

ekvious, descrihehle hard.

were delerst. -

___SR An avent or operatinf.

, ,g ,, ,,, , n , g , , , ,,,,

condition occurs ,,, ,ow,up = masw equipt ,

which causes or coula e , *] ,,,, ,,,,, , ,,n .

causee loss of life , evuge of a doye er a= cert or severe injury to e ep station personnel. sad plu nus.reten

,ene a e3o nerequire or a,su,vi,ive.e e me t -

e,- ,

ae.g., stum generator, ser. .

w oe,e urtw m 1 ant remp.

ou.it es. An tar'aet. tle .we 1 d uine an event. i e old n o ers u u e. i n esee any mau.e1 erruutamoet Y. IJpgraded from

. conditionally signif- ,_,,,, ca. oner serplein) .

ieant w m1, .

D5teF//46 Time /670 Determination F

)(J.~-.

1.3.240-1 Rev. 12 l

f ~

\

PNPS FAILURE AND MALFUNCTION REPORT FM No, b -086 EVENT DATE +# / d EVENT TIME _ /6I3 A. i l EVENT DESCRIPTION (FM ORIGINATOR):

1. Activity in Progress

( 2. Circumstances Leading to Event _/t/04M4 L O#('bo n A) b 88 s'" /H W 7" )

p t-#c/ eve #

/->44Jou ) #rs warseo

3. /soansu vnses C v o 16D 15 i Event Descr1ption - Glos A nr 1 919Csn>O UT4Aso u M1~/u r h u eifT.

Mj7strYr urxMr c

JtVro A v. /hM/ Discn4MA M40rit ~ , a te Musaa ~rv M a nn ut~ {

4.

Probableby Reported Cause _ SCAT ~ 4-(AMx6F PA ST" 2. 'i A 71 // vn o B.

DATE _+t/// ///

CORR

1. VE Event (N) ACTION INITIATION is Safety Related - (WATCH ENGINEER REVIEW) I (N) Event is Tech. Spec. Related System No. / O I

2.

(N) Tech. Spec. Action Statement Entered Tech. Spec. Section J 1. .D 3.

ECTIVE ACTION JNITIATED

~~h' _6 At ~;5X0 _Ler ~ rs.d 64 o#~ % doeue/

N i Maintenance Request Issued

@) (Y ) Procedure Utilized M.R. Number R4 -/o -/ 4

3. LCO Procedure Number ENSATORY ACTION (To mitigate effects of f ailure)

N0HG ~ ALoct-coo &- 7'O Cnf X JJ 4

vuocun L. r-uf*'r DKLAMA NOTIFICATIONS Telephone Reauired Criteria Time a)

' Notification Time Limit Notified Eg_rson Contacted (N) (Refer 2.2.17) Muc ps. Mg . 24hr, 4hr, b) (Refer 2.2.17) N (via 24 fggy/ C dp4 A c) ,

WAT (Refer 2.2.17) 4hr SA ihr O/o ZW/?//90:56 cert /

NGINEER SIGNATURE />" + /

\y C.

v i -

EVENT

1. PL REVIEW - (SHIFT TECHNICAL ADVISOR REVIEW)

TATUS JUST PRIOR TO EVENT a) (N) Rx. Critical b) Rx. Pressure _/ 0/'$'

2.

d) . Mode SW /2. v.) _ e) Rx. Pwr Lvl jeMMvrc) Rx. Coolant Temp. _ f fo Y APPLICABLE PLANT EQUIPMENT STATUS a) Redundant safety systems available and operable are: A/A- 6C87"tPC/

b) c) Najor Safety systems not operable are: 4 #C/ 2 M r'ssa vorr/ou) /No#

concern

{

_t-o5T n / PA-IMAM 6~rrd s f /AAMALL um{N r~A n/ 4AR f'T 9 R ~ hv (

A M/ /h<rncM/ cnurn Atf,o O (-/L . '(_su L /) n k f u eG MiE l

. 3. SAFETY ASSISSNENT I a)

(Y) y Constitutes previously inanthe accident FSAR. or malfunction of a different type than evaluated b) c) (Y g) @(NJ Reduces the margin of safety as defined in the basis of Increases probability of occurrence or consequence of an accident, answer

4. is no if action required by Tech. Spec. is taken.

{ SAFE Y SIGNIFICANCE (Fill out a copy of Attach. D Proc. 1.3.24) a) Significant 91 nditionally ignificant

).

$1GNATURE .

- __ 2. ONotSionificant REP G - (COMPLIANCE Rfi/IEW)__ 6/ DATE 9- //W 1.

t

' 2. 15(N)forLicensee recogsnendation: Event Rpt. (LER) Reconsnended Per 10 CFR 50.73 Section: 64MIv)

_ l PC T meo /S

.GM S+w n h elis rt_ptch vit. no Lx' 6'D 7 xrMclhXtth ct SinalU 0 +fniO 91+1 '

v.

i

3. @(N)

Basis:Root cause shalysis and corrective action plan required?

Repadn bh as im and ruvind L CA L nt-to If yes, Attach. 8, Proc 1.3.24, or eg'uiv., shal'l be completed 4

Lead Investigator _ Shtn uullma n Lead Group (N) ORC Review Required? R H fd V A t D G TDre

5. O,'Event Y "Stanificant" rkkcfAb3 A/At: fy c% VP-Nuc &,-t Ops: ' Person Contacted _ ALrxh Da te 4/a,/n, PLANT ENGINEER $1GNATURE M 4.

M DATE 4h5/h STATION MANAGER APPROVAL

(.

' ORC REVIEW - (If required) DATE ORC NEETING NO. _

DATE DISPOSITION -

Nethod 4 COMPLI ANCE GROUP LEADER SIGNATURE CLOSE-0UT - DATE AUTHORIZED By DATE

_ . _ . _ _ . _ . . . - * * ~ ^ ^ " ~~

h. ,

l

FM No... ZG-b1C Date 4 - j ]- f 6 FM -ROOT CAUSE AND CORRECTIVE-ACTION PLAN

1. Verified event description. Synopsis:-

W k's\< a k 4 i in- fow(r. /^2 ?-0A t)v6 To 2 e 8 z' 2A g vsua (cpct) GGlw(yCtosto, l-CO

/v' /6 N PA-6 S C-VA 6 14LAn M CA MG t# Oh) /] LopP l PC( /VM(? i))r(tdn/L66 IV f4D VL, G W x *2-4-ifru

. CSO C 7:7.D.3.) D G c tity-S v u s S vA u. E v'Gur Fou 2.-

.Vf0V Most pro T~ COUTAhkIWT~ 750v/oT"i CQ VA.vl-S /A'Of, le cause:

-69 8 ,'~) 8 0 2 9 0 VAWbS W Wi $~ (b l_5681'3~.

O. ActjoSs' Coccq ect Cobpleted/

R&T 0 -Gwo v c.

e Te sr Planned v o *9 w f f (inclufc>$*fE'd.2 y ,.. g e e 9e f A-s e x ces ( 2-ea A r urce GATG)

4. Recommended Actions to further determine most probable cause/or preclude recurrence:

/$tvDL y f G AS FOvuO fA)L vA-6 ,

. Completed by:

, Agreed to:

Lead Investigator Lead Group Group Leader M Date Y ~~ //'~ 88 or Chief Date 1.3.24B-1 Rev. 12

M ATTACHMENT D -

(ar d l

INPO SIGNIFICANT SCREENING CRITERIA j 1

i sia.sracaarr eneromo.Au7 stausrs' cant nor arausracaert 1

l i sa. t.wo w r.e 4 red..d. : f yn.=

nw.. eeriera.re .,,,,,,, ca. A. .H..C.. d.t sd.t.ure.we.r.

yne., a. wa. sa .a.e.le r d f.i.nie

d. s ,ern.e,

n. .

'"""'"**'* e or. v1 1.u seu w t.n.adery, p n. ry , . n u ss. m e surs or.6 s.i 3.e.,r.desi...

nd.ri.e..e n vr .sp.u -

an. t.w.

t. w .e.s.en t.it u .. e s

, s.t .: pr.u n no s- A., a.o 3 aut . {

e,. . . .e = rus e.sa e

. ,. - 2.a , eu. i .

l sl. Thr er o.re f.13 r.. eesur e 9 33. Par.o .pr 1 d.rt.g th. . . t. a ).r . th.p3 f.11 r.1..d &..t 6 t .g.,

. one.r.3 d3..rrer. fits..sie ..d. s. j u es a a ~ u t. tr. -"" as a .a 1

- . ,1 n . .. r a.i m:2;.ag,:,';*-==>

m i,.4 d..an u n u. .

. u u

e ... .. ..u,i.,..u., es. aa. =^. .,, r..o , 2.a er wau.sa

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., eas., m ied.na.-l. .u.,

n.

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aas- **8 - Ma a . ~~~. .

.... ,, . s.r... ..,

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.,. .a.a.r

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ra. .

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u. ..... . ,. u. wi- . .a ., e nu o. . n.a , ..

u...i.,.r..

4 ., . ,4 .2 . . .. u ..

~ ~ ,.

n u.., :g g ,sa u:; g ;,c :, , ,, , , .., ,

.u.. ,,,,,,,,C3. a pr.ble. ro..It. 1. '.ff- W6. W r.dul.,s s' u ;8;;gia",;;,a!** a . se -.. ~1.entam- . l a

t- n s a.i., --n.

a , u.. ,..

n u. r.an. nu. . . . . u m .n.erauu. ,, , , . ,3 a., ,

s... ny Mgh? ,,,s. D.mmagt.d.4 fr condi-o r.l.... er esp .r. U '"*NI II'"AU'**S' D.ie W e. 1 sis m-s8. Ms.1.J.trati... pr .d.r.) er

. c.ur u? d.

.t. .

e,.r. tion.1 .rr..r. .t.

e.m.- """"" C4. A 4. 19. er 1. ..fo.rt.rt.g 4.fi i . 18 O matted fd e.t m.t r. ult.4.'ir.e p3..M .3 mi.u.d

.t p rf.rs

.f.ty r. pares..u.

r .u 41.g e

th.

3 e .i.u..

.ti.3of.f p.t..s.u..ry th. defic.i..ey f.

.14.

de cr&b.bl. h.rd-er t.11w .11.r.1 4 l

l

. w.r. d.i.n? - l

,,,,,,,,,,SR An event or operatinf, es. A pr.o e dt I condition occurs u p = . s .: gims 1.. . s e

which causes, or coulo **"* -

. . su w pr nt. === . .ws cause. loss of life , u n .: se ny. .,a .rt or severe injury to e r. win n- ;

,na s u.pr.ess : a u .. i .. *-

station personnel. p.u. us i 3.,. ,4, M ,

i i

1.. r. sw . we .

w .re. i..

r. rsu

. . ... sus pae, eu.st, es. u ur .n..u . .

dui.eu n.n.

. l w ye .. ca ur usv. s.

o . 1.e.t t .m.e .i .?

I Y. Upgraded from

, conditionally signif- _ ce,owesup1.sw.

1 cant u . tm a Dhe 4-lPf4 Time //if Determination By _

Rev. 12 1.3.24D-1

. - - _ _ - _ - ~ _ _ _

1 L

l . 2n .*.? - -

1 ,,

i ~

gyv$d ?.' '

PNP 5 FAILURE AND MALFUNCTION REPORT o.

~$

es * *S -t.D , ' ,;

FSN NO. 8(**Of'L tytNT 9 ATE W/Vh EvtWT TINE Ed!5/$

f f

-Orw ry/@,

f L Ag fp g h ,q & N & ,{ . 8 '1fa Qj row,;

2. Circiestanejs Qh 37. rd t*%;'g p M rv a.wLeJding , to twent NeMe 4 M o #' W u . 4 % f % .4 ,

" ~

, N p /f 3. _ Event bescr7ption -rb T.as t e m ad a. 'wird at FM R u Wo .w"

-,:. &Q

+.

yN;, f 1, .

.P/ff Asf ft) R*,fa 4c Anno w tin kost M W.) Gew me An /fa.tv wMsf n Jere A w M CG hm. rA+ y/W L+ ano aA

[~. S ' M4.6 -

4. Probable CKuse ""'"" " *

Reported by _ 1 L h lv N a ha v M hh .4 s ' '

s- g

. .3,,5 .~ . J :- DATE _ idAv /fL

.r' r.

i* " 4-t -.. B. CORRECT

<#* ~

1. (Y) E,') (vent ACTION INITIATION is safety Related a (WATCH [NG.1NttR RfWitW) .

' *(i *4. ). *f ~f -

L (Y (V)

I twent is Tech. Spec.' Related och Spec. Action Statement Entered System No.

Tech. Spec. Section .

/

'*At 2. COR , E CTION INITIATED weu a are s k yi :T h' "". I.)a .. _'

s h t (a

, &/d R. Mnm n 8

1s M m ir Ah .4.a um.'

2 f. r t .4 { , i g , ,, if N) Neintenance Request issued N.R. Neber - d -/n-no l~ _,g "g Procedure Utilised

g.g4., . . Procedure Number-

., t 3. LC0 C PENSATORY ACTION (To sitigate effects of failure)

L .%' 2 us ' .' J l M i}

f d, ,, ,3. # Y .t '4. NOTIFICATIONS Telephone Time Criteria notification Time Limit I

. h.,g*e y ..wt- :., ys,l (Ref er 2.2.1T) Nuc. Ops. Ner. notified Person Contacte 1 24hr, 4hr, Ihr J g . C /7/#g%r 1

,.,y"- g. 4gj a -.:

. : ( (Refer 2.2.1T) NRC (via EN5) 4 r. 4hr. Ihr ,!

',. s* ,/.,,

c) (Y)( (Refer 2.2.1T) CRPC Grp Ld

P, 4 .*.~ . . Q,; w. . . .' . 3 WATO ENGINEER 51GNATURE e -- -

. W . - ^;,p M m

' ; \y

.g

. 6 VENT R(Y!tW - (SHIFT TECHNICAL ADVISOR REVIEW) e ky'.ce, g ; == 4 gd

1. PLANT 5 JUST PRIOR 70 EVENT 6..e L*'s.? vu- a) (Y) Rs. Critical b) Ra. Pressure D 1

7%ET + %*. d) Rs. c) Rs. Coolant Temp. //2 CC ]

.C 4 we SW e) Am. Pwr Lv1 A

2. APPLICABLE PLANT EQUIPNENT STATUS g%,

Q 7,.n h[.. -((k.) =-

a) Redundant safety systees avellable antogenb1p are: A / /-8 9" m e L%-

b) Safety systems not operable are 3 (f tf u' w re m t_ M rl. ' Mn eI;y&.p jd s.W si.e]c*

) **0 0f C *nC *'* 'I^'- N ' Y' b'**k" I^' W ' '

.%.ff C.18. tGMV V ,. T *2'i ' Y4

,%. 2 % I

. 3. SAFETY A $NENT ThM;.M/N.$'i;"'. a).(Y) N ' onstitutes an accident or malfunction of a different type than evakuttet .

-h *24hDo W3%'4'8M 4

previously in the FSAR.

$dYN4,,h>Nr.W b) (Y) 4 -D'..*pf" c) TV)

Reduces the margin of safety as defined in the basis of Tech. Spec.

Increases probability of occurrence or consequence of an accident, answer l l We-h MXe4GL. poa

~-

4, -

is no if action required by Tech. Spec. is taken.

, 4. SAFtTY SIGNIFICANCE (F 1 out a copy of Attach. O. Proc. .24)

URE W ?L

!M 4%M ). REPORTING - (COMPLI ANCE REVIEW)

A

^T-f;'.%

W , h' h' 74-'*]*

1.

2.

(V) (N) Licensee twent Apt. (LER) Recommended Per 10 CFR 50.T3 Section:

Basis for recommendations

/ '/ ~ ~

. q ,t:+ ~. $ . *s q i y%j zja ;

b 3. (Y) (N) Root cause analysis and corrective action plan required?

MM-y*-

h[- s. Attach B. Proc 1. .24 equiv., shall be completed

,- - ' (yc ce'Ar[ pg 2 by Lead Investigator ( Lead Group hg[/'

- sb ph!h y 4 (Y) (N) ORC Review RequiredT S. If (vent *31gnificant* notify VP-Nuc Ops: Person Contacted Date U

PLANT CitGINEER SIGNATURE DATE

. .J 7,, @ ' . STATION NANAGER APPROYAL DATE Qn . w.-- .

(. DRC REY!EW - (If required) y' ,G r"y?v . ,

(l'*y

DRC NEETING NO.

DATE q:h0

~ 13.'A ? . "'

. O!$P051T10N -

Nethod Ma* 1amp hd 4 ..&

4' E 4.,$ 5g.1# O : COMPL!ANCE GAOUP LEADER SIGNATURE 0 Aft

' 4 7 .' . 'f . 1 + . !

i. CLO5t-00T -

i, kki*' b AUTHORIZED By DATE v u . ~. m - tc . .u s: e] i '

p1 . ;y. 1.3. 24 A-1 Rev.12

,. . 6 ,. h'. .

~~ . r.~ ; ,q~

+

)g : y., -

a 2 .: cm y , e s t

f g

, .' *p/ h 4

*t ,

y g .c h'. "'

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W.e.:. T; _

Y, . ,

~ w4 .* . ;6%. ..

2. su'. l & ,,

_ _ _ _ _ _ _ _ . _ _ _ _ ___ [ # '

' - 1" o

FM No. -

Date .l FM ROOT CAUSE AND CORRECTIVE ACTION PLAN

1. Verif.ied event description. Synopsis:

,J D. l\ <

1f \

l_t is 2: Most probable cause:

1 h/

3. Actions Completed / Planned (include , dates): j 1

1

4. Recommended Actions to further determine most probable cause/or '1 preclude recurrence: !

l Completed by: Lead Investigator Agreed to: Date Lead Group, Group Leader or Chief Date a l

1.3.248-1 Rev. 12 f b

j 1

? 5'.1

, ATTACHMENT D .

[ I INP0 SIGNIFICANT SCREENINC CRITERIA sis rraeant e.wan as.: sas :rshawr m.e sienne.nr 1

ss. v w a ew.wm w. sunw erne. a. a=n=s.r e _ ca. a. u.ord. r.en n. m e m ,,_,

ems .rnam. s. us. a n.ues. rw e.uiiee= ,n..

r. -t a=. ,.um.,vs.u na w.. a= ry . s r. w .mw.e. r e.rsu.a m s.e ,ra.u,.m es.sw.

.n = ==.s.n neeaus

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an www w .=. tenwm w e . seu ns. ,w u..*. -3.,in. ,u. se .ta s a .

ru : errn.u a. -. -

ru, pr - -1 n

w a . ==a . ~ +

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inu .

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. i.,.. .,.,,=

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s

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new au maan er e. u . o . .

ss. amaa.s ep.r.ti. tr.st .. pr.a..*.e.1 g. m-er e

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d. a.d. 13. .c f.e r.1.g i

41 nt.1 4.und ret..dA.g .dh.fs c.i..ey pet e 6f.11 46.nu.r.1 4 d u

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afar s.vur-m. . 3. -

eend.ib.bl.r r =hor 6-

.b.i.u.. J w.t. d.i.d.et1 -

_SRAn event or operatinf, .

condition occurs """" es. A ,s.r.u.

o

re es.ap

=$w d u 1. . *s e . .

which'causes, or coulo , ,"[ ,,,g ,, ,,,,, , ,a cause, loss of life , u e. . as s.r. w 1 e rt or severe injury to . .g.i n -

He ps .e t.h. ,r 61 ,

atstion personnel. ~.s. .a, .u,.u s p.s.u .s.. .. u n .3 . r ,

4 r.

st= ensue m2sw. s ,=, ,

eu.n -

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muus cre i ut i

1 l

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.- conditionally signif- ,,, _, es. o r t pteal .

feant

w. .tru .

4 Dittep///ATime A/M pm -

y .

Determination ny 1 W4^ m 1.3.24D-1 Rev. 12 I

O age h

e e

e O .

i l

l E________________.

(,

"W " M.10 NDP84E1 Ta me:. Enr. Deputy REQUE$flN0iNPhiE1MM"b from: CW#d /4/NfT, bd Y/iis _

ESR Num W fr Enr. Requestin0 Dept. Y. 6ste

, "",e*nen,,r S. l(Jo//m & ~ Mf l Date Final Product Neathd e6 .EQ ME, PrepredBy: SCdollWan f .

aroup 0564 P R b/R7B5# GrcremetAree oP

/

L ygi, O k 5 4 / 4 00 TV fE CT (/ - S A F GP V ,

54 k u 0 A T l o N BF S I S -

P N P S Ppblem Summry(incl. Root ) T64 @*W 9/06/M IW3 es /A)AS// l400 c=0perf Y

~

Drn u chf +0s 90e9

~R6 4A ' Ce A l- E olo u e n. Noris stu A p rio r. *

~La-mit1 W ikawls a Yp ti n t (Da r- t I

4 Attachments YES/NO 4 I

Suppstod Solution (s) (IlL#o$ti End/ aod DEpse6dm 9AIPSW cfoosdinn uliFk Ncord

~

Da a > <r>L 0 % % /dcti 6 (D E u alua 4 Ulaed het %urWeiv6 h 14 d.esen i /et clur valves //)M/-h A A d fr Leed 0roup Engineer -

i .

Attachments YES/HD Target $ tert ired E . Product (ORE tr L &4xira0 #0 set 44u /rapet ' Terpt Finish t

EV4 4T@0 et bosm furomae/W4d af 3%r#4D o t- " / ta* de Plant Condition toimplement: ' ' wo l

15 < t/ d to6OA M No. i ting Doc.k Ref 1711e. J;E. A40u)a rd & _

l Sy/f Ef awn Fo/zca fle-foev- Mtschments YES44DJ instructions j justification / impact if Not Performed /%x #w.o d #m A4mr< ]

j AD $$ fS.fR L noen'u & {D d e r Nd conmerd iM Cif Mdcun , Deodat+ i Ik)\+k G +m r %D {rmk i (D Pc foues k cm -2 = ==h' W

\

Attachments YES/NO 3

syn.Name l?WP, lae %g, EPCC RC' 8 y number /O, /% 23,/)

Qimponent Name HjaN*1 f/cr#t//M Comp.No./go'lyMM29ag Quality Ctese S Prfority A > Input Orp.tdr. ,

Apjirwel(s) ) *

)

l initial w {

lbution: Original to 0..Nuc. Enr. Deputy Manager for Enr. Protbetion Distribution NED(see abwe) f Praparer PS&CC(Tracting)

R ng Nt. Mr.

PS&CC BraintnREC'D AN 2 8 g Om M1 j OnsilsADM EXHIBIT I input Orp. Engr.

otteis)- '

~

STA OFFICE j l

~ " "' A4.10 . kip 64E1 REQUESTIN0kPMtTEi$"Lii

/ kkh ,, ,__ . NIE T3 Nic. Ery. Deputy From: CM 5 Pterupr Ihr Enr. ESR Num Rapseting Dept Pigl. Dele w

,,non,,,r c 6%//sen 2K -ML DetsFinal Preukst Needed ISF(_ GMAW I .lELE, PreparedBy: MA8Nef - /Y/MVN8D erao 0.SS8P /70d 7kKraqgatAra lb? .

yg), T E M P E R 4 T U R E pl o'NL t o E!I d Cr .

Q ,-

O P f. W R C L. 6 S S 2. Ql l f El!

Tb W)0 CNa/ A /s*< f

. Problem Summsy(incl. Root Cause) '

f. ,

/AL % n. 44, din h A VE fine H RMC;hiv4

l I.;

foressare /es k a af ee d m w a, -

Reg Anel. Due Data

.e j ~~ Attachments YE5/N0

~

D#

Suggestad G vn/ua4 I#4 M Mr-/Nw/6-Solutign(s) WiiMe a r d AL fit o %to lDo1 -2A$

'\

17 t+ K p ipinn '

(on A ) ' Wa.1<rl Ve da tocM nJdws.r s M< sewerh" Leed0roup Engineer M /#4Ra v at ;-/eam vo rdr ax , .

i ,,v

'3 --

g ~~ ~

Attachments YES/NO

- DesiredEng. Pro &ct 1~ a rAe e:A' t^) C E J A L OAnd w l m W0 Terget Finis Cu o ersfc d - A g Est/Nours .

1

<< i Plant condition toimplement: W.0. Mit

" Aamunt& '_

Supporting Doc. & Rsf. P/h< W$# F oEcs #EPoEC__ -

Altzhments YES/NO Instructkre _

Justification /impactif HotPerformed fREured hB/'e-

~

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darho drom 81SfV' sa h d, .

Attachments YES/NO, 8rs.Mae 2IM sys Number /D ._.

ComponentName F/#6 Comp. No. 8"-O~ O - -

l Onlity Class d' Prfority A Input Orp.Lt. ,

Apprwel(s) J@/%_,

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'Ibution: Original to 0..Huc. Engr. LWuty Menegar for Enr. Proiction Distributtart NED(see etwe) i m Preparer HEC'D A 2 8 E Preparer PS&QXTracting)

Requesting Dept Mr.

PS&OC Braintres Olr out M1 Onsite ADM STA OFFlCr-M iBIT I input orp. Engr. >

other(s). . ,

- _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ i

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s A4.10 NdP84El !

REQUESTIN0kP%EY@"5 ""ddhyf//14//5 I

Ia mm. tar. Deputy from: C J /V4 E875 ESR Num Nanager fbr Ety. Requesting Dept. Y. date

%$enso, S. A b ro F '3~* i

> I Date Final Prodst Needed 1.566 8(/a Av l ,2G,Q, B,,

Prspared By: 5. S. uh 1% n /

Orcup OS$6fF ,/IP//R TRs k FE:ercoat Ares nie

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_foa.n b) b'1 a Jfad v e ,< ' asa J Me 9mA id valJes k

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LeadGroup Engineer 1+164welsidhesh'ois 256 hsis , ~

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Ntechments YES/ND

- Desired Ery.P SJ E Grd he W imtato Target Start f ps' k kaD .for Terget Finish !

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Justifiestion/ impact if Not Perfamej Jzg s-Arrhp _

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Attachments YES/$0 S/s. Neme @d SA Number /0 i

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b Inpd Orp. tt {

4hrovst(s) -MIV ~ cc:

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. . .. e w l lbution: Original to 0..Nuc. Engr. Deputy Manager f's Cry. Product 17 Olstr(buttert NED(see atme) !

cc Pryperor grn W 2, 8 ' ' '

Preprar '

PS&diracking)

Rtry:s'.ing Dept. Mgf. ^

PS& CC Ersintess Otr W ,1 onstteAct1 STA OFFICE EXHIBIT l .(fb. Irod drp. Engr. j Oths'(s). .

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r Target $Wt DmiredEnh.5h Md6 EvALu4TW/tl W2iuo - /w/at/44 Terget Finish (U Pernurw4 v,'sY,,, h - /e c.m., 6 // w Est./Nours Plant Omnditionsimplomant: .- W.0. k Aczount No.

SupportMg Doc.& Asf. 12 4 e 0 A. QJ-b/2CE /2.epr#,

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Priority A input erp.Lt.

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REQUESTING DEPARTMENT USE 31 A4.10 N0P84E1 l

re Nuc uty rrom: c541a-#//hg S / 4//$/6 / @@SE&

ESR Num M or Engr. Requesting Dept'Tif. bote

,lo,, Leo,r s.a/d e , _ N-/2e i

Date Final Product Neeed I d./s 3/ 4 l NED USE D.6 UO$l$hdentN( / 4//C/ffe RECEIVED prepared ey- ,

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oram 67AT/oAJ TEQ}. Tatny. ant Aren APR 17196c. l R#4 yR VE 5 2 8 842M L (4 k oteuTY MANAGER Title l S V /> L V & 1/0N em Summary (incl. Root Cause) b Yk VN N b b l l A I COD I 8 L64KACG b CAkA*Gb MVA770\U th F 74- R H D.' ALAf241. % ^^*L DU* D*t*

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M L-12Eb AY Lt 8 4 39R fek%AGV LeadGroup Engineer B R Henrek 0 .

A Attachments YES/fgv Tar #

gg DesiredEnr. Product GUh///fM/A/6 51//f6067/ap./

Est/ Hours Plant Condition toimplement: N.A. W.O.Na 579 M Steporting Doc. & Ref. //Yb40 7 erst W ,_

Attachments YESdG/ Instructions Justification / impact if Not Performed y /86#,8 N N T

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Attachments YES((NO) b Sys. Number /0 3/8 h Component Name il 6 D9 8 V/MV85 Comp.No.

Prfority input Orp. Lt.

Quality Clees (O I Input Orp.tdr Apprwal(s) M $$

Second

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'buttort Or @nel to 0..Mic. Enr. Deputy Honspr for Enr. Production Ofstribution: NED(see ebwe)

Preparer PS&OC(Tracking) g; R ng Dept Mr.pKD d Dir Out M1 PS&OC Braintres InputOrp Engr.

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Tc ph m Ery. Deputy Neopr for Ery.

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La kneIWPNa Prchlem Summary (incl. Root ceues) lath at ac/wva# -

Dressafe (MSk u n1 Wa% Its N H W.79sitoxv

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Aetnunt NL SWporting Doc.k Ref. flyC rM K Pd/dC G 4%-VMr Attachments YES/ND instructions Justifiestion/ impact if Hot Performed B#5<re d #/d r 4o W af % frott in 6Ill rHcAnes I Er a VH1 Yt 9 [dhts ae % +-a

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Quellty Class L'9 Prfority input orp.Lt. .

Apirwal(:) [///d4 '

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Requesting Dept Mgr. '

PS8a: Braintria Otr out M1 --

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2EE SK747f.-G p) .ss-oo no-Mo/.sy8 l

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34) 'Ihrust,1bs. ~/7.r# e85. 9pwM

35) Torque, ft. - lbs. M N8#-

36) Stem Nut Drawing (A/DV) **r ff shu e 8

37) Limitorque Order Ib. Jengr -G - kg$sgo)NgNq 38) 39)

Actuator Serial Ibh_

Valve Serial Ib. co-s er nur ,*re-* <s+

40) Special Features Added Asa u e.e ca yrtjse=" Ard.

41) Limit Switch Assenbly (Material and Color) /r/re,rs, ye- /~ ca 4..

a) Gear Housing :Fewrs b) Gear Housing Cover c) Drive Cam 4W4pm sw d) Insulation Ner Meour s ,

e) Rotor A es,rs , weess - c.4 4, .

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42) Torque switch (Material and Color) Naeaar Sewsh cdse.

a) Cam Shaft ,eer,ypaasw '

b) Insulation w,T eek ur e l

43) 0-Rings (Material and Color) .

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PURCHASE ORDER NO.

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Page 1 of 2 p.,,,

S Sk' 7V84- G 6) 33-00 Mr -/co/ J3V5 VALVE M7IDR ACIUNIOR IRTA

1) Bechtel Purchase Order /OS9F-d*- SF4C IG)

2) Valve Tag Nuser MPa-/ss/-sys

3) Tnroue Soring Part Number to-tea-ooff-/

4) .p.3_LE7 ED

5) Dial Settin'6 Posic' ion 4.

6) Maximm Dial Setting AM

7) M2nber of Gears, Limit Switch 9 8)

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9) Nuuber of Trains / Contacts .E/F Torque Seat or Position Seat. 74Ncesm*7-

10) Direction of Stem Nut Operation ccw fe opse

11) Manufacturer and Grade of Imbrication in Gear

12) Mousing Wiring and Limit Diagram Switches anxw Nervu 17-/ de Msj. *.fmid- Ar /"J.l..s..n

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13) Dimensional Drawing oa-y/4-o/p7 4 q

14) Valve Size /e nd 4 i

15)- Valve Type s u r

16) Differential Pressure (Design / Tested) J#o,j c.s.

4

17) Design Temperature "Jy W ar - 4.

18) Stem Speed, Inches / Minute e . 7.ru m.

19) Stem Travel, Inches /o4y' e

20) Stem Dimensions (Diameter, Pitch, lead, Hand) /ft, fy, b 4#

21) . DELETED

22) Size and Type of Actuator SF oo

23) Actuator Enclosure Type A**4'd4

24) Motor Rating, ft. - lbs. Arn. e.r. l I

25) Motor RPM /roo

26) Motor Enclosure puen. -

27) Duty Cycle, Minutes /tdes

28) Voltage / Phase / Cycles 74d/3/40

29) Torque Switch Type (Single or Double) m. A4*/#d4 N8& 7*'*f"# 5"'4# ~

30) Motor Gear Set Racio huses-ses# m #" # MT*

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38) Actuator Serial & ar, Valve Serial No. ems.rvers' )yig)38 j

39) .

Special Features Added AroF t t se-rn ** -

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i Pilgrim Nuclear Power Station Rocky Hill Road '

l i Plymouth, Massachusetts 02360 l l t

SPECIAL ORC MEETING #86-16 l

J.A. Seery's Office

' LOCATION;.

RAT _E_;:_ February 19, 1986 ATTENDEES: J.A. Seery, Chairman P. D. Smith, Member R.E. Sherry, Member B.E. Eldredge, Member .

S.S. Wollman, Member 4 A.A. Shatas, Member G. Fiedler, Alternate J. Rogers (NED)

W. Clancy (NED) (Telecon)

P. Cafarella (NED) (Telecon)

G. McHugh (NED) (Telecon) -

P. F. Giardiello QUORUM REQUIREMENTS SATISFIED ERINCIPAL TOPICS:

1. Acceptance of ORC Meeting Minutes

2. Safety Evaluation 3, Procedures

1. Acceptance of ORC Heetina Minutes 4

The minutes of ORC Meeting No. 86-05 were accepted as written.

2. }afety Evaluation Mr. J. Rogers (NED) presented Safety Evaluation (S.E.) #1918 to the ORC for review and approval. NED was asked by the Operations Section to prepare this safety evaluation as a contingency for dealing with a small amount of seat leakage being experienced by Valve 1001-288, which is the LPCI outboard injection valve for B-loop.

I Page 1 of 7 l

I I

.]

h 1PECIAL' ORC MEETING #86-16

~

I This' safety evaluation. changes current LPCI valve _ configuration from

.MO 1001-288 (closed) and MO 1001-298 (open) to MO 1001-288 (open) and MO 1001-298 (closed)~.. .The latter valve,: acting as an isolation valve provides greater assurance for. isolation and ' prevention of leakage-because ittis a gate. valve. The original plant configurat. ion was with

! the'M0 1001-288 valve.open and the MO 1001-298 valve. closed. .This safety evaluation provides the option to restore this configuration for the B-loop.

Mr. Rogers reviewed .the safety evaluation in detail with the ORC members.- The situations which were evaluated due to the configuration change included: l(1) the.effect on the LPCI injection function, (2) the effect on the_ shutdown' cooling function, (3) the effect on' the isolation function and (4) remote shutdown functions associated with Appendix R. .This safety evaluation is applicable-to A loop if the change is desired for-that loop as well. It was' concluded after a lengthy' discussion by the ORC members that none of.the functions would be compromised by changing the configuration. i A' discussion then followed as to whether leakage of water past~this valve was'in excess of air leakage limits for Appendix J LLRT. .

Presently,' maintenance efforts have been successful in stopping the leakage by this valve. . Administrative 1y, it has been decided that it is unacceptable for the'1eakage alarm to come in more frequently than once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . .

-} lt was pointed out that during RFO]6 a successful LLRT.of 1001-288 Valve using air indicated a leakage of 1.9 liters at _45 psig, well below the limit established by Appendix J. The Appendix J limits are l conservatively established in anticipation of some minor degradation 4 from routine operation during the subsequent operating cycle between tests. A calculation performed by one of the attendees showed an approximate leak rate of .003 per At 1000 PSI. This is a small leak rate at the present ant conf guratTon. )i One of the ORC members felt that it was important to elicit from NED a i way of equating LLRT (air) with existing water leakage by -288 valve. .!

He felt that the plant should not be shutdown to perform a LLRT. '

A telecon was set up to include Messrs. W. Clancy, P. Cafarella and G.

McHugh. It was their conclusion that present-day calculations equating air leakage to water leakage are not defensible, would not meet Appendix J. criteria and would.not be accepted by the NRC. Mr.

P. Cafarella said that past data indicates that the Local Leak Rate was good even when the leakage alarm came in af ter 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . He recommended that this type of past data be examined for establishing j acceptance criteria. W. Clancy requested that the station walk the LPCI line for any packing leaks. He concluded that he would confer with his Department Manager and also the Pilgrim Station Manager and, upon this concurrence, do some informal leak rate calculations.

Page 2 of w________u___._._.._

~~

SPECIAL ORC MEETING #86-16 The ORC concluded'that Safety Evaluation #1918 did.not involve an .

unreviewed safety question and approved it for use only if the leakage .

alarm came in. .

4 It was"also pointed out that several. procedures and drawings would have to be revised by Station Management and Nuclear Engineering.

A copy of Safety Evaluation #1918 is attached to.the minutes'of this meeting. .See Attachment 1 for further details.

3. Procedures The following~18 procedures were reviewed by the ORC, determined not to constitute'an unreviewed safety question, and approved for implementation.

i Number Title Revision-n- 6. B . 21 - Emergency Lighting Units (fixed) 2 (SRO #86-15) )

4

' Purpose and Summary of Changes This change adds circuit breaker identification, properly-locates lighting units.and properly identifies the names of building areas. These changes reflect actual plant conditions.

Number Title Revision _

'8.5.1.3 Core Spray MOV Operability Test 13 (SR0 #86-16)

Purpose and Summary of Changes Changes stroke time acceptance from 18.'O seconds to 20.0 seconds per S.E. #1918.

Nu'mber Title Revision 8.5.1.5 Core Spray MOV Operability 5-(SR0 #86-17) from Alternate Shutdown Panel Purpose and Summary of Changes Changes acceptance criteria for stroke time from 18.0 seconds to 20.0 seconds per S.E. #1914. I 1

Number _ Title Revision 8.B.6 Preaction/ Deluge Sprinkler System 12 (SR0 #86-18)

Page 3 of 7 l

l l e_-____.

,.. n SPECIAL ORC MEETING #86-16 Procedures (continued)1 -

Purpose and Summary of Changes i

' Change to make written section of. procedure to match numbers on sign off attachment.

. Number Title Redision

.6.5-272 . Calibration of MS-3 Mini Scaler 3 (SRO #86-19) i Purpose and Summary of Changes Allow calibration and efficiency determination using plated metal sources versus filter. paper with deposited source. Procedure to be redone with proper sources as soon as practical after.they are available. '

~

Number Title Revision 2.3.2.1 Panel Procedures Panel 903 Left '9 (SRO #86-20) .

Purpose and Summary of Changes This change. corrects typographical errors and includes good operator practice for' relieving excess pressure.-

Number- Title

~

Revision

}". ' 3.M. 3-24.1 Limitorque Type SMB. Valve New Operator Removal Purpose and Summary of Changes To provide procedure for proper removal of operators for' maintenance (work presently done using vendor manual). Addresses INPO, SALP and EQ concerns.

Number Title Revision 3.M 3-24.2 Limitorque Type SMB 000/00 Valve New Motor Operator Overhaul Purpose and Summary of Changes To provide procedure for motor operator overhaul (work presently done using vendor manual). Addresses INPO, SALP and EQ concerns.

Number Title Revision 3.M.3-24.3 Limitorque Type SMB-0 Through -4 New i

Motor Operator Overhaul Page 4 of 7 ,

l:

L I

SPECIAL ORC MEETING #86-16 Procedures (continued) ,

, Purpose and Summary of Changes

To provide procedure for motor operator overhaul-(work presently done using vendor manual). Addresses INPO, SALP and EQ concerns.

'_ Number Title Revision 3

3.M.3-24.4- Limitorque Type SMB-5' New Motor Operator Overhaul Purpose and Summary of Changes To provide detailed instructions to perform work currently done using. vendor manuals. Addresses INPO, SALP and EQ concerns.

Numbhr Tltie Revision :

3 .'M . 3-2 4. 5 Limitorque Type'SMB Electrical New

' Checkout and Adjustment Purpose and Summary of Changes. .

To provide procedure for electrical checkout and adjustment (work presently-

-done using vendor manual). Addresses SALP, INP0 and EQ concerns.

' Number Title Revision 3.M.3-24.6 Limitorque. Type SMB Valve New Operator Installation Purpose and Summary of Changes To provide procedure for installation of operator.(work presently done using vendor manual). Addresses INPO, SALP and EQ concerns.

Number Title Revision 3.M.3-24.7 Limftorque Type SMB New Disassembly / Removal Purpose and Summary of Changes To create a procedure to enable maintenance personnel to properly !

disassembly / remove Limitorque Type 58-00 through 58-3 motor operators. Work is ;,'

currently done using approved procedure 3.M.1-il and vendor manual. Addresses '

INPO, SAIP and EQ concerns.

Number Title Revision I 3.M.3-24.8 Limitorque Type SMB New )

[ Reassembly / Installation

{

Page S of 7 l

- --__ )

l. ,

SPECIAL ORC MEETING #86-16 t' . Procedures-(continued)~

'l Purpose'and Summary of Changes j

To create a procedure which will enable plant maintenance personnel to properly perform a reassembly / installation of Limitorque Type SB-00 through SB-3 valve

-operators. Addresses INPO, SALP and EQ concerns, Number Title Revision i 3.M.3 Cleaning and Agitation New of Station Batteries Purpose and Summary of Changes

.The purpose of this procedure is to provide instruction to personnel of the proper way to' clean batteries and the proper way to agitate battery electrolyte.

Number' Title Revision 5.7.2.16 Re -en try 3 Purpose and Summary of Changes i Delete "II3 "unless the urgency fer a re-entry is so great as to preclude the performance of these steps", and 7.dd ")f necessary to preserve human life or I

prevent imminent core damage, thi; stop may la eliminated at the discretion of-

$ the emergency director". 3' Number Title ~ Revision :

7.3.25 Particulate and Iodine Monitoring 9 at the Main Stack and the Reactor Building Vent P'urpose and Summary of Changes I The changes made to this procedure were done so as to clarify present analytical practices, correct typographical errors and eliminate some l unnecessary precautions. (DR 1489 related) l Number Title Revision l TP 85-124 Administrative Control for E203 New !

Project l Purpose and Summary of Changes To provide administrative centrol of E203 walkdown project.

Page 6 of 7

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L SPECIAL~0RC MEETING #86-16 ._ c, . .

Hira , ,

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" Prepared by ,

Approve'd by

. -s .

PFG/lo-g _;

Attachment:

- l '. Safety' Evaluation'#1918-cc: Standard Distributt'on List.

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Page 7 of 7 i

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_1.__.______. . - - _ _ _

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NED Proposed'Chasige Safety Evaluation SAFETY EVALUATION No.:.'li(F' -

.j=

PILCRI ! .'.I' CLEAR TOW.h STAT!ON ' )

'Rev. No. O ]l PDC /PCN System Calc.

Initiator: Dept: Group: No.: Name: No.:

=Date {

.T.c.Rops NEo stsA -

RR -

]W dan *46.darnand Description of P posed cha T Vebte um QuhtNot e,nth 0 test 0/001or -2 experiment:)el S' 2 (closed Dbiof t-29e fooen)

~' "

A10/ cot- 22B Yo,neos) aed M0/oci-2R 8 (clo. sod).

~SATETY EVALUATION CONCLUSIONS:

The proposed' change, test or experiment: .

l 1.. .( X) Coes Not i ) Ooes increase the probability of occurrenc< rir con- I sequences ai art tr.ca. dent-or malfunction of equipment topor.a it to safety previously evaluatec in the FSAR. -

2. X' Does Not ! ) Coes increase, the possibility for accident or malfunction L vi a different tine than any evaluated previously in the FSAR.

3. ()G Does Not,( ) Does decrease the margin of safety as defined in the basis H ter.any.tecnnical specification.

SASIS TOR SATETY F.VALCATION CONCLUSIONS:

Yk caw.k valw cevtfhwuth% is as s & fed a6tve. . A o001- 196 valve _

(s a del,e valu a.,ul L %M -2.9 A value && ante valve . %L m cF e ash %\an ae u ineln W m Ivo cre s.b L a 3b d n e_< m ei *F oessk-uiso p, % , % , p s,%, W 1 ma,st 6; waju + 2 ~ de fe Wuy pw _

m t% Mfn t ea L L.PCI Lilothk LabN M L affuf n k sku%L,.

A fu,a K 'L3 ) M. e ffor f- en L is.ela h& Mchn -.)(4)re,ute 4twMLvat fuchh s As's' e c. ato L wM M R ,

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Su_ o //su kid s kan fx . ( 2. o f 2 )

Change Change

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Safety Evaluation j SATETY EVALUAT]ON No.: /j j f(

PILGRIM NUCLEAR POWER STATION-Rev. No. O , j

k. APPROVAL

( d This proposed change does not involve a change in the Technical'.

Specifications.

(d . This proposed change, . test or experiment does (,) does not (d involve an unreviewed safety ' question as . defined an 10CTR,-

Part 50.59(c).

(d This ' proposed change involves a change to the TSAR per 10CTR-50.71(e) and-is reportable under 10CTR50.59(b).

() Comments:

The safety evaluation basis and conclusion is: i

./

(V) Approved () Not Approved f ( 6 (, y(e

\ w. 2, Di M1pline Group Leader /Date W Supporting Discipline Group Leader /Date B. REVIEW / APPROVAL I

() Comments: it b)$s d,1ln2SE (n is also as we 11, +o % A loce f Ioepb.hble T%

D PDPs to evo k, L4 neeiokurs Mlot t % uw v.sinees,%% W & aw m ad.

U l.h W lth8(9

%SA Group Leader /Date '

C. ORC REVIEW

() This proposed change involves an unreviewed safety question and a requests for authorization of this change must be filed with the Directorate of Licensing, NRC prior to implementation.

This proposed- change does not involve an unreviewed safety ques-tion.

l ORC Chairman b Date ,9!cFg ORCMeetingNumb}er { l -

M-//2 cc:

Exhibit 3.07-A Sheet 2 of 3 Rev. 1 79tri)cy /-GAc .P 6-/ i

l n.,

..- hTC 12 3-B 14 ' i PILGRIM STATION FSAR REVIEW SMEET-

References:

l Safety Evaluation: bib Rev. No.: 0 Date: 2" l8 U#

Support a change *

. I

~

t List FSAR test, diagrams, and indices affected by t.his cuange and corresponding FSAR revision.

Affected FSAR .

Section Revision to affected 'FSAR Section is shown on: I Preliminary Flnal-Attachment 1 S## C W

vut ny#.f Attachment 2J%,6 Tables, w d,'l W.

(5 MA y%

-Attachment 3

.' '1LL c k La--

.g Attachment 4 1

_ Attachment 5

~

Attachment 6 O -

PREI.IMINARY FSAR REVISION (to be completed at time of Safety Evaluation preparation). -

-Prepared by: /Date: Reviewed by: '~ ~

/Date:

u

~

Approved by: /D l

u &hM ate: d /$.$(o .

FINAL FSAR REVISION (Prepared following operational turnover of related systems structures of components for use at PNPS). (1)

Prepared by: /Date: Reviewed by:

, /Date:

4

l. -

(1) Attach completed FSAR Change Request Form (Refer to NOP). I Exhibit 3.07-A Sheet 3 of 3 Fev. 1

(

.a n., , a i.sn e er -it

)

NLC123-B17 '

Safety Eu lua t 3..n SAFETY EVALUATION WORK SHEET

'No.: /9/8 O '1 Rev. No.

A.

Sy.Lem/ Structure /Conponent Failure and Consequence Analyses.

System /

Strutture/ Component Failure Modes Ef fects of Failure Conne r.t s 1.

N b Y A M b bM f U 6 t W u Y C b dri' n.ba+cN Y Ys ibeh Cl ' b _Y(u) y Chs ,$ct p tea o'osL 5 sl5cus 5 n'o ><. ,

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General Reference Material Review '

1

{

f,. FSAR CALCULATIONS }

. REGULATORY l SECTION PNPS TECHNICAL SPECS. DESIGN SPECS / PROCEDURES G l

l l

B.

For thefor likely proposed hardware change, identify the failure modes that are i the components consistent with FSAR assumptions. For each failure mode, components.

show the consequences to the system. .etructures or related Especially show how the failore(s) *affects the assigned !

safety basis (FSAR Text for each system) or plant safety functions FSAR Chapter 14 and Appendix *G).

Prepared by G V

'i 3Dete N .

q '

NOTE:

l. It is a requirement to include this work sheet erith the Safety Evalua-tion.

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PART-1 ,i 3 '

L Determination of the Number of' 'B' RHR' Loop Pr e s su r i z a't 'i on s 'Wg ,,

g.- i ,

7

'When leakage existo. inL the 'B' . RHR loopi;ag oressurizat ion occurs. - Flow-D . element FE 1048B:is seksitive to'.this pressure SnctbatTa. response.in the f r

~

E associated.instrumentottoniFT 10498 SORT:1040-158 responds by becoming more

~

negat ive.- This .pher}omena -is ' r.eceived and recer ded on . flow recor der FR1040-7 on Panel 903. This : phenomena was. observed in; the Februarp 498F RHRL I(

' b'I .#,

II pressurization events.and became atoredictive too1 % hen the' problem was' '

active.- I' i;

' tf The. ' B' ' loop channel (the) black pen L of FR1040-7 has-a live")or. .

. p As-pressure-increases:in the line.:which is.in the' low , f i upscaleLzero.

. pr essure par t : of the ' system sp,he. pe y ~ resp onds -by t e,th di49, downsc a l e . L'h grt ,-#

Y , ,

. the. RHR; high pressure, alarm ahnunciates the..oper ator relieves 'pr essur e O- ~

d-the Torus via the test line./'The pen lresporids by spi k ing' Upwar d and ther,:

~

i; set tling bac k - to the pre-eveinj { posi t ioru ../ -

e, y;

j: ' ' , ..

1 s ThIs phenomena, has!beenQsserved by theauth'or 'severa1 STA's - Watch; y j

Eng ineer s . and: Oper at i ons p er sonnil . : When the B' -- RHP loopfat er t es-t' was conductedi the FR1040-7 pen was ' observed. .This"same phenomena' repeated-L under ;the controlled test 'condihons. Figures F.1 and F.2 ar e recor der

, chart copies.from'FR1040-7 that show thephenomena/' / , ..

y n.

1.

f

- Since this phenomer.a :js known and can be cor,related to; the 'B' .RHR loop

> pressure eventsi 'it was used as a resea'rch tool by th'e Task Force. .All ,

' r ecor der _ FR1040-7 char ts wer e reviewed and t he .' B' loop response was-recorded. This review notes the occurrence as "B loco ever,ts" in the roug?. ,

notes. The notes' were then tibulated.by count ing the number c f event s' or.' a I

y

given day. The tabulation.was conve/ tid'to a plot of'" number o f: ' B' SHR '

loop pressurization per da y - ver su s\ 't ' me i " . The entire 19?5 and 1954 data has;been reviewed and recorded. The, plot isFigure5'inthebodyfsfthe ,

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I i CALCULATION SHEET {^jgo*M37my 30,
" APPENDIX F - PART.THREE" PREPARED BY DATE l "FR 10 0-7 Rm IhTA"' ,$, CHECKED BY DATE Edison .sewam APPVD BY DATE
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~~SUBJECT:~~
~~SHEET ~ OF~~
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~~CALCULATON SHEET - ra {aggoRIZATION ND.~~
) # APPENDIX F - PART TmEE" PREPARED BY DATE '~ ' "FR 10 0-7 RAW DATA"- sams$ - CHECKED BY DATE EdisoII APPVD BY DATE Q JUBJECT: j/7f f SHEET M OF - C rw Map o'7(f 7 / if 7,/6 Y l'//9'8f ll ob -tyoo prou) p owe lis s (weves) , . it//t/er steo - 5 rooy pr&<> rerr NSR \ .tipe/er 8&eap flood ords 00 to , io eo, /75o ,
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~~CALCULATION SHEET TAL 1 CAygoplZATION NO.~~
APPENDIX F - PART TmEE" PREPA#ED BY DATE ~ " CHECKED BY . FR 10f0-7 RAW MTA" DATE w.
~~soms%s)on Ed APPVD BY DATE f JUBJECT: j % g,. Q [D C/0 SHEET / OF , Byen /~/-8(.o SR O~~
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CALCULATION SHEET gyJgg,7,og ,g,
'" APPENDIX F - PART TmEE" pnEpAnED sy .DATE 1 ~
CHECKED BY DATE "FR 10LO-7 RAW DATA" somsf}l2> Edson APPVD BY DATE l JUBJECT: /98g SHEUTdOF
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~~CALCULATION SHEET .. fyT*h37my y,gn~~
~~.e.~~
" APPENDIX F - PART TmEE" P +,MEPARED BY DATE . 1 ;. , ,
~~x8*M, d.g . M E M ED BY DATE "FR 10 0-7 RAW DATA"' Edison eewm~~
~~?/ .~~
~~sovo av oATE (~~
~~SUBJECT:~~
SHEET OF gtL/8(o B l w f' 4V M ll 0 0 1 ??;' ' y, gg .fl g sf% Bisof.so W essa . . k Ygg G, (a loop tu^+ ooa d /y7/ P) E 5ag Nsn D-
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MD = f oot ' n E.Co, FORM 3930 g
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CALCULATION SHEET CAN 2. c/ l f m. _ _ ggw- AUTHORIZATION NO. q
~~
~~ENDIXF-PARTTfREE"~~
~~.j PREPARED BY DATE f6 g g,7 g gn '~~
a > CHECKED BY DATE /0 e < Edison APPVD BY DATE /p~ ef l
~~#; esswam 4/ i~~
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~~SUBJECT:~~
//[ g f SHEET OF ]
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iCWcG[LATION SHEET AUTHORIZATION NO. 1 1 ffq7APPE)CIXF-PARTTWEE" .
.&.FRE, FARED BY DATE r#'d, - & >
VR 10lO-7 RAW DATA"c . mas .3 cHr.queo eY . g' g- m3 3 DATE l E s' son Apra6 SY DATE , eewer -t i f3 waJEcy:
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~~CALCULATION SHEET {^jg'o^n'lZATION NO.~~
# APPENDIX F - PART TmEE" pagpango ey oa7e FR 10LO-7 RAW DATA" offh CHECKED BY DATE Edison APPVD BY DATC Q-
~~SUBJECT:~~
SHEET OF char + pap tus vis y/v/86 Y/y lE LccP in S/tuiocoseoety (nu a tex ) " NSR C Y/9 8ou+ + .sda4'wt ue/ap. e or>s 9,/9 hb NOO[ k / h4 Oddd dd!N f y,/tqmco B tocp '.snu Hoa>n cooby ok o sec
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ADMINISTRATIVE CHECKLIST FOR RHR WALKDOWN Date. /f [d.__ Team Leader SIGNATURE INI'TI ALS Area to be wal k ed down:).8_k_3_.1/J3_I l lA.S.QO./11.k_f_d_8..."f A' OTHE0gfg_f Mo ESg _ l Majoe C oao on en t s : .f.QLLtB.24$_ A fbeAl.t_%2T, b_-e.$.M'ASJ1.stIb9~.)$$Q k!)!O /OO/ 2s. JhD__I_QD.I'".7AA_0~stBP._C.Ld__$C E.4@f_h_fif!!.11AU.W_G_?"C_lW.*_'t.$ bx t_een _ v.4m._ .?J. eau ?& . _ Hw_w m&.(std _ C uL .s_JBc) _ p $% AM CL V Sc h M b .g -{-u)*4*'t /OO/~E98 GHS f0 0 M 4C /'t'
, At t a c h men t s t o b e ' u s e d : ..d_f _d _h fffdd /SO_d6d d'$d _ ff_d _8_M . 2.ifidp _ _ A_W_.1. gs_12E_p _ A _0_ _% _ A tl._?_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
~~REQUIREMENTS~~
~~.'/ . NRC Representative has bAe iftedofwalkdown and has received NITIALS copy of walkdown plan. *r _ / _p_.b_____/_/2 _2 ./_ _ _____~~
~~TIME 6- t #rt +0 ' /Nf'. Skosgd &hlE i~~
~~, j . _~~
WISPCS Approved MY If.!TIALS Walkdown team briefed per Proce dur e- 1.3.39 Sec t ion VI . C. ITIALS _[ fil'T ALS RWP Obtained h -[M l t _____ Watch Engineer's approval given
~~#MI t/ T7- / 7 #F 4- (.$ 4 Mow.< (ce /, }'-~~
Walkdown Commenced .( 2 .6.[2____/ .,_[ [_k_d ______ INITIALS ATE TIME Team Members: Leader _ 8f_44'I________ _ Q fa a c _i_________ % _( _2_1_ _ _4_ _ _M_ _6_ _M_ _L_ g ggy___ _DE___0AevE4,________ _ kff _
~~.&.%i2.Maacau.. .m!Rt. !~~
uL&A/35e f.d 0r
l i Attachment i V8LVE INSEECI1QU IEXIEBWoL1 sFILL 0UT BEFORE ENTERING AREA OF INSPEC, TION ValveNo.hP_/,,0f[.~,.#T_4.
~~. T yp e o f Va l v e _ _ _ _ /_@.. .h. d_N .,__ _.,_ ____ _ _ _ _~~
Mfgr.__ M./f_6.d_4 N .___ M0 Type / Sire .,_ M 8.d.,- ,)...,____,__ .,___,__ Present Valve position-(from CR)__,____l.. Q,C_(f_4_ ., , _ _ ., _ _ . sNOTE: Annotate'as appropriate if valve is a check valve. ! V8LVE_______________________. ________________________________YES_____80_____ Body - Evidence of thermal damage (i.e.. paint : : , spalling or discoloration) : : ! Bolting Inspection - Body to bonnet bolts appear loose lv/ l Operator to yoke bolts appear loose > l l : *
. Packing / Gaskets Bolts appear loose : :* - Evidence of Leakage h Stem - Damage observed' l O
~~.: 7~~
~~- Improperly lubricated : :~~
Insulation - Insulation damaged / missing / showing : signs of leakage . : As found valve position _____h 9_h _h . .,_ QEEBoI0B- _ Grease - Leaks at Motor / Operator joint !
~~! ', / V~~
- Leaks at Operator / Stem Area : : - Other leaks noted l Other : - Mcvement of Valve / Operator / Connections // ! - Cover plate appears loose y , //
__________________:_Elecitigal_fler_tettata_lecat ___________: t Obsttralient and description of any item under "YES": pen $ wr.,s Led.g(unncL b Lea 9 % Bena hja:n,g R;oq~1 LeeKim'FDD "d W evw t o 5 m ( A Ws e_ r : A yoYR , 3., avprigtM1)msex / BL3 A USW'N s N _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _
N ff.& $ . ? Ruhr S to , Attachment 4 -) L \ SUEEQBI INSEECIIQU 1 TvpeoISupport._b.6.0 $1. fly.hE. ._blO.6._AC1( Loc at i on o't $uppor t: ...@ __f.98_4IJ_s_i8,9.d_..d_(2_b.... fN. i l l.
'INSEECIIQU- .YES- UQ. 'i Is there any evidence of suppor t damage? )
~~I If yesi. sketch support showing damage location. ( Attach sketches of all supports'in area then mark up sketches) m l 4 ,~~
~~@h i~~
~~1 l i l~~
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~~' Attachment'1' V8LVE INSEECIIQU IEXIEBuell~~
~~FILL OUT BEFORE ENTERING AREA'0F INSPEC, TION Va1ve No.tiffd.@/_-,s?88 Tyoe of Va1ve. 8 ._h_{f_8.6._.___..._ ....~~
~~NFgr . N_O__L.. W___ W____Y__._ NOTYoe/ Size.__$_M_B__~__T__...__.____..____.. Present' Valve position ( f r om C R ) ._.._ _ _@ ff)._ _. _ _ _ _ ..~~
~~NOTE: Annota'te as appropriate if valve is a check valve.~~
, .V8LVE....___.........______ ...___.________ ____..._____ ..___YES...._UD.___. ~ Body - Evidence of thermal damage (i.e.. paint l l spalling or discoloration) l' :.
~~Bolting Inspection - Body to bonnet bolts appear loose' l iy l~~
~~. A ' Operator to yoke bolts appear loose! !/~~
~~l l Packing / Gaskets - Bolts appear loose l l[~~
~~- Evidence of Leakage - h[ h _~~
l l - Stem - Oamage observed ! : M O.- - Improperly lubricated l l l l %'f l l Insulation - Insulatton damaged / missing / showing l signs of leakage l/ l As found valve po*sition. . h $,, _.... ___ l l l l QEE88IQB Grease - Leaks at Hotor / Operator joint l lY
- Leaks at Operator / Stem Area l l / -j I I - Other leaks noted : :
~~f ! Other l l l~~
~~- Movement of Valve / Operator / Connections l l - Cover plate appears loose l~~
~~l j' )~~
~~........ _________:_Elttitical.fitE_AQEtatt.129tt____________ .__.. .____~~
ObsttYaiiSCE and descr iption of any item under "YES". 3 M 51th % A$_,_ol at FM (3g y} 3 h
i
~~I i~~
~~1 Attachment 2 l E12160 INSEECI1ON IEXIEBNeL1~~
~~FILL OUT BEFORE ENTERING AREA 0F INSPEC. TION.~~
~~PIPINGDESCRIPTION___j[.,[.__J2.C.,d___/_Q_______________________________.,_ PIPING-LOCATION __ __[_N_k__h.,_b_Yf.__[f$_U___N_0.U._$_T_/_h___3________ Ho /w/-278 i i~~
. . I N S E E C II O N _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Y E S _ _ _ _ _ _ U O. 3 -.Is there any evidence of overprestare? l l v' l l - Is there any evidence of thermal ' damage? l l ,,e; (i;e;. paint spalling or-discoloration) l l l l Is there any physical integrity problem? l l 'L/ ~ - Are there.any piping' attachment problems? ,
L#
~~- Is'there any damaged / missing / wet insulation? L' Observations and description of any i tem under "yes".~~
M G~ C ,.2 h +4. G L 4 1 ? l l l 1
1 4 4 Attachment 2 L-E12160 INSEECIIQW IEXIEBuot.1 . 4
~
~~FILL OUT:BEFORE ENTERING AREA 0F INSPEC. TION-~~~
~~L PIPINGDESCRIPTION____/M.'.'._(2_4.~_[S.....__......__....._.__.._____~~
? PIPING LOC ATION _.50 A.//8...(8.kL/f_..b?R,9d_'_f}QC_d___Pff_(_D2f_~2_M,_&_ 6*r/7~ . I N s e E C I I O N._ .... _ _ _ _ _ _ _ .. . . . _ _ _ _ _ . . . .. . . _ _ . ... . . . .. ._ _ . . ._ _ _ _ . . Y E S. . . _ _ 0 0. ;
~~IsLthere any evidence of overpressure? ' : /~~
, l .I - Is there-any evidence of thermal damage?- l l / '
~~(i.e.. paint spalling or discoloration) : :~~
~~- Is there atey physical' integrity problem?~~
y:
~ - Are there any. piping attachment problems? h, ! - Is there any. damaged / missing / wet ins'ulation? /
e : 1 : Observations and description of any item under "yes". ftew trTYx ~~nu TS / d y ert ,p, gf
~~N N key. -~~
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~
Attachment 2 .j E12180 INSEEcIIQ8 IEXIEBuoL1 nFILL-0VT BEFORE ENTERING AREA 0F-INSPEC, TION PIPING DESCRIPTION __ d _,,,_ $_d__'/ 6 ,,,._,,_____,,,,,,.,... _,,..._,,. .,_,,...... PIPIN0 L0 CATION _.8.'.$/!$__V_k_L$___h?2.Y__.$$ .._$?)_O2!_~k_9_? .. p /fO /o0/-5Q78 l ; l i 18SEEcIIos.________________________________________ _____.___.__YES______UO. l y'
~~- Is there any evidence of overpressure? ! l !~~
~~: ~!~~
~~Is there any evidence of thermal damage? (i.e. paint spalling or discoloration)~~
~~f f/~~
~~i 1 Is there'any physical integrity problem?~~
- Are there any piping attachment problems? :. l - Is there any damaged / missing / wet iniulation? - '
~~y c Observations and descript-lon of any item under "yes". i V Q S a ls b l a C sC&l0/^ eel GA~ $lO /00l ~D 5 ALSO~~
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~~-Attachment 7 IU!IButEUI READOUT.- .....IUSIBUdEUI.UQ ......LQC6I10U.................EUU;IIQU..._......LQteIIQu.~~
~~p'g gemaa no w-29s f Ho foo l- Mg.~~
'IUSEECIIQU .!E2 5 , /*b Are there any process leaks at pipe tap? I Are there any process leaks at instrument rack? Aff4 . - Are the instruments loose on the racks? 4/,4 Is the wir ing/ conduit ' damaged' AgIf -
~~Are'the gauge. pointers damaged?~~
t/ ' AN N' MC N' m 4 k Is there damage or movernent in tubing runr>? A)(4 ;
~~Is there indication of leaiage in tubing r uns? Aff4 )~~
~~...................................................... ... .....I........... -)~~
What T i n,e /ff C. dry..f fr.' itoe s t hbg a u g e r ca d i n g 7 2......$.9.I. .. A c/on OTHER: Describe anything answe-ed yes o- any :ther observations. q W e.t'Aong 400 skhoyaje /rtshl * % Wo Yst y l'i W r 4i Y1'p,pe ps), y;&g ~ g 7( g
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~~'B' RH R ' VAL VE SCOM SUEEQBI IU!EECIIQU.~~
T pe' of Supperi _M2dC___E4&__2_W.G_ h_8.94__/e65_l...Eff._F4.[AZI/,Mp_EDJ bcatton of Suppori ___Nd__________________________________________________ IUSEECI!QU YE! SQ Is there any evidence of support damage? NA j If vesi sketch support showing damage-location. ( Attach sketches of all supports in area then mar k up sketches)
~~.i j0 .D/SC AEfK AM6l Es 'No7ED , fiyggg pgg Als R H A SjsrE M pipe s upp.ccw se rms m an.~~
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.O .d ADMINISTRATIVE CHECKLIST FOR RHR WALKDOWN Date. .[._ Team Leader . , , . _ _ _ , , . .h . INI,TI ALS .
~~SIGNATURE , Aeea ta se wa1 ked 4own:.Dr.)(.dd.:..l,se?).t..LQpf_-3.3.B. .to L.Mf!!?,bfE dis'*/& NaJoe co ponents:.!A91.-3.3.e.f.ntatueJ..Vlat.)Le1e.e..fx..hCf.T..B. 6xe)~~
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~~. /.0.a L:.6.B.B..& d . X .S.L B.............................-..~~
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-[$.Obd[.-.----. -l V ) _Y .S .,. .$. & . .,$ 5...........-.....--.........------------------
~~8 REQUIREMENTS-~~
] . ) .1 NRC Representative has'be if ed of walkdown and has received. .
~~ITIALS copy of walkdown plan. . .. 8 [e...././.d l.E D. ... . .~~
~~+0 #fR, S.f r-os TIME !~~
fil# d d4TE I.h.,@. WISPCS Approved [U A V/f] INITIALS i
? . i s /j ~ Walkdown team briefed per Procedure 1.3.39 'Section VI. C.
l
~~../~~
~~INITIALS~~
. .. RWP Obtained k "* [ j INITIALS . . . , . Watch Engineer's approval given W' INITIALS ,
Wa1hdown Commenced .... . ...,___...,/......,...... . .. INITIAL $ DATE TIME 1e.. .e.be,., Le-e,. $ . n . L ..... '"
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~~.- 1 Attachment 3 l~~
CONI 618dENI EENEIB8IION INSEECIIQN mFILL OUT BEFORE ENTERING AREA-OF INSPECTION d L Penetration No. . sa /. .......... INSEECIION~ IES 80 Is there any evidence of physical damage? L '#
~~' (If YES. explain): . i W~~
~~e. PROVIDE ANY OTHER OBSERVATION OF CONDITION: _ hpAI6~~
.1
~~r . Attachment 2~~
~~'E12180 INSEECIION 1EXIEBN8L1 '~~
nFILL OUT BEFORE ENTERING AREA 0F INSPEC. TION PIPING DESCRIPTION .. .k. _ _ . ;k. . _I_h_ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ . ., . _ _ _ _ ., , _ PIPING L0C ATION .8A[.Mf_4f___/f.fd_--I88. _~7~_.866(fl2Cd_7.qY..,.[_~.'N_k. .
~~. INSEECIION_ .___.. ...____________ ...___________....___________YES._____UO. '~~
Is there any evidence of overpressure? # l l l l Is there any evidence of thermal ' damage? (i.e.. paint'spalling or discoloration) !
/ ' - Is there any physical integrity problem? : u Are there'any piping attachment problems? :. V Is there any damaged / missing / wet-ins'ulatlon? ! l /.
Observations and description of any item under "yes". q N4: f YO& *
~~% - a& l6k k2M".3/O*(g .- /~~
o i h l l, l I l
l Attachment i V6LVE INSEECIIQU IEXIEBuoL1 aFILL OUT BEFORE ENTERING AREA 0F INSPEC, TION Valve No.. 2 @ h._( [_d _ Tyoe of Valve 8 .'.# [.Tt_/($.. h 6 f d _______ j M f g r . . . [QCM_kf ; ..,_ _ H0 Type / Size ___ d_.,________________________ Present Valve position (fromCR),,__N#4A_d__C(f,I,@, _ , , _ _ , , _
~~NOTE: Annotate as appropriate if valve is a check valve.~~
VOLVE_________________________________________________________1E!_____80 ____ Body - Evidence of thermal damage (i.e. paint l l t/
~
spalling or discoloration) i : : Bolting Inspectson - Body to bonnet bolts appear loose l lu Operator to vote bolts appear loose l A./,/A y neo Packing /Ocskets YA
- Bolts appear loose l purama ' . . sa m p ng.o Evidence of Leakage l _
Stem - Damage observed C - Improperly lubricated Insulation - Insulation damaged / missing / showing l4 v signs of leakage l : A s f ou n d v a l v e p o s i t i o n ._u,p,(4 3gg ,,,, _ _ ,,,,_ ,,
, gestro l R As ti c. 4 QEEBoI0B ~
~~Grease - Leaks at Motor / Operator joint l AJ,/j4 . l l~~
- Leaks at Operator / Stem Area l l - Other leaks noted ; ;
~~Other : :~~
~~- Hovement of Valve / Operator / Connections :~~
~~j l~~
~~- Cover plate appears loose !~~
l
~~A ;~~
__________________:_Elttitiidl_flts 42226tt_lSSat_. _I________ ObsttvetiSon and description of any iten under "YES": r.% cvorme er we nwo tut s A n.~ m w o vs a s.
- N' A!4 6 Caweg j cg, /Asva sfeMr>R $H F T HAye er,p onc g I'l DM'U4 4 BKt TTtc .rusua riou A-up p g'1( " ' ^ < . Pkseme M omeusrurp0 m *"n-up p,e e nw .p m m ,., n , m OW Purc<n) muy, au w 7., #NW 90 A tu g cpmg , , "h% W ' FMugig Q l
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~~Attachment 20' f: 4 l~~
~~, a, )~~
212160 INSEECIlodIEXIEBuell . 1 ... sFILL OUT.BEFORE ENTERING AREA 0F INSPEC, TION $^, f i
-f PIPING DESCRIPTION _____ _ ~ /O -
j
.~ \ ' PIPING LOCATION ,,Pggtg./CL G_,, ,,/_ff[_.2_M .___ N M ff,/,,h,h,/" S.___,,. ,,, , , 9 ; a . T yr; . ,- i 3' + ~
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~~_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ y E s _ _ _ _ 80. .; e, c. : : 1~~
~~- Is there any evidence of overpressure? ! lJ LLa l~~
~~((t c : : j t~~
~~- Is .there any evidence of thermal dantge?~~
~~(i.e.. paint.spalling or d i sc ol or a t'i on )~~
~~@l: '~~
1
~~- - Is there a,1y physical integrsty problem? : :~~
~~1 ...~~
- Are there any piping attachment problens? :. (f , ' " ,- - 'l ]!l, - Is there any damaged / missing / wet indulation? '
~~Observations and description of shy item under "yes", j .[ q' - ;~~
^
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~~(Attach sketches of all sus.g.or t s ir, ar ea t hen mar k up steiches) il~~
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.79 M6 hE INSPECL OW IEEIEBuell- J .v9 r , a. s.m . e y a
FILL.OUT BEFORT,I,GNTLP.ING AREA 0F INSPECTIOK,

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~~Valve No../.d /~.d M ., Y TypeofValve._d___.id_d_3[.______________- il a '~~
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~~SVEEQBI INSEECIION g gc7,6g Type o'f support ______________________________________________ _____________ Location ~of Support ________________________________________________________ [ .'~~
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IUSEECIl0V YEE tf0 1 Is there any eva der.ce of support damaget / If sesi sketch sapport sho ing damage location. ( Attach sketches of all suppor ts in area then mar k up sketches) T)tE(L& G)A s no EJt oEA)LE of Ascottm AL-QIOii T))s ptAcew&A>T 02 Guptoo nY OAw/16e : 1 THE SP(LIDG- CAO LAI M IU ITS PQopert_. ; (oc.o 66TnA)G. ~ l e - i i i
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l' IUSEECI!0U ygg gg Is ther e ani .evider.ce of sung.or t damage?- / If <es.. sketch support showing damage los*3 tion. I Attach sketches of all'suppor ts in area then mar k up sketches)
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ML20236E712

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