ML20004C925

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IE Insp Rept 50-293/81-05 on 810224-25.No Noncompliance Noted.Major Areas Inspected:Discrepancy Between Licensee Response to NRC Which Stated That 20-inch Containment Isolation Vent & Purge Valve Had Been Modified
ML20004C925
Person / Time
Site: Pilgrim
Issue date: 05/05/1981
From: Robert Carlson, Christopher R, Matakas R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20004C917 List:
References
50-293-81-05, 50-293-81-5, NUDOCS 8106080045
Download: ML20004C925 (31)
v • d • e


See also: IR 05000293/1981005

Text

{{#Wiki_filter:. . O U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION I Report No. 50-293/81-05 Docket No. 50-293 L Mense No. DPR-35 Priority -- Category B Licensee: Boston Edison Company 800 Boylston Streets Boston Massachusetts 02199 Facility Name: _ Pilgrim Nuclear Power Station Investigation At: Plymouth Massachusetts Investigation Conducted: February 24-25, 1981 Inyestigators // f _ e fl 7~a ! l -//2 'l?! o R. KRith Christoph r, Investigation Specialist / date f7 / OL ' dite Richard A. Matakas, Investigation Specialist date l Approved by: [ MMA^- - d 8/ l Robert T. Carlson, Director, Enforcement date ' ~ I and Investigation Staff Investigation Summary: Investigation from February 23-24, 1981 l (Report No. 50-293/81-05) Areas Investigated: The investigation was conducted to resolve an apparent discrepancy between a licensee response to the NRC which stated that the 20 inch containment isolation vent and purge valves had been modified to ensure that the valves would not open beyond a 45 degree open position and the findings of a routine NRC inspection that determined only six (6) out of a total of eight (8) valves had been so modified. i , i 8106080

. . . . I. SUMMARY This investigation was initiated as a result of an apparent discrepancy between a licensee response submitted to the NRC on May 27, 1980 regarding an interim commitrent to modify the 20 inch containment isolation vent and purge valves and the fiadings of an NRC inspection (50-293/80-30 pertains) conducted from October through November, 1980. The licensee response stated that the 20 inch purge and vent valves had been ,

modified to ensure that the valves would not open beyond a 45 degree open ' position durir.g power operations. In contrast, the aforementioned NRC inspection + determined that only six of the eight 20 inch butterfly valves had actually been modified. Interview of the individual primarily responsible for drafting the response letter determined that the intent of the letter was to reflect that only those valves that are or could be opened during power operations were modified. Additional interviews and review of station operating procedures determined , that the operating procedures were changed in September, 1979 to prohibit the opening of the two valves not modified until after shutdown. The interviews indicated the discrepancy may be a misinterpretation over the . wording of the response letter vice an attempt to misrepresent the status of the work done on the modifications. It was also confirmed that the require- ments for the modifications were neither costly nor time consuming to complete. . + e " * ' " " - -= r -- -- -a_- w , , - _ _ _ _ _ _ m. , , _

- _ . . _. . . . ' . - 2 II. PURPOSE OF INVESTIGATION The purpose of this investigation was to resolve an apparent discrepancy . between BECO letter 80-95 dated March 27, 1980 which stated that the 20 inch containment isolation purge and vent valves had been modified to ensure that ' ! the valves would not open beyond a 45 degree open position and an NRC inspec- tion that determined only six of the eight 20 inch valves had been so modified. , J . . 1 s . -,-m-- ,y-gg<r ,.7,. 77 , -pg ,- ,- - 7 , y -- 4.-, a e - -r---. y, __ y c* --- +~me- - , , - , - y. -,-9 - - , , , -,,-~g --,,+-avyg,--g.-, - , .

. . 3 . . . III. BACKGROUND On November 29, 1978, a letter was forwarded to all licensees from NRR, Division of Operating Reactors raising concerns relative to potential failures affecting the purge penetration valves which could lead to a degradation in containment integrity and, for PWRs a degradation in ECCS performance. Specifically, should a loss of coolant accident (LOCA) occur during purging, there could be insufficient back pressure to ensure proper operation of the ECCS. Accordingly, licensees were requested to provide a commitment to either cease containment purging during power operations or to provide a justification for continued purging to include a demonstration (by test or analysis) of the ability of the containment isolation valves to close under postulated design basis accident conditions. On August 21, 1979, BECO letter 79-158 to NRR provided their evaluation to justify unlimited purging for those valves involved in containment differential pressure operation including the 20 inch butterfly valves. Subsequently, a 10 CFR Part 21 report was received from the manufacturer of butterfly valves raising concerns regarding purge and vent valve operability. On October 22, 1979, the licensee was requested in accordance with 10 CFR Part 50.54(f) to commit to an interim position for containment purge and vent valve operation pending resolution of isolation valve operability. Specifically, . the licensee was requested to: " Maintain the containment purge and vent isolation valves closed whenever the reactor is not in cold shutdown or refueling mode until it can be demonstrated that; all isolation valves greater than three inch nominal diameter used for containment purge and venting operations are operable under the most severe design basis accident flow condition loading'and can close within the time limit stated in your Technical Specifications, Design Criteria, and Operating Procedures. The operability of the butterfly valves may, on an interim basis, be demonstrated by limiting the valve to be no more than 30 degrees ',o 50 degrees open (90 degrees being fully open)." The licensee responded on December 19, 1979 saying all isolation valves greater than three inch nominal diameter used for containment purge and venting operations are maintained in the closed position except for 24-hour inerting and deinerting. Additionally, in BECO letter 80-95 dated May 27, 1980 the licensee provided the following conclusion: Our analysis has concluded that the dynamic and pressure loads acting on the disc and stem will not cause unacceptable stress while the valve is closing during a design basis LOCA if the valve is maintained not more than 45 degrees open. Therefore, a design modification has been developed and implemented to ensure that the 20 inch purge and vent valves are not open beyond the 45 degree open position. Station Operating Procedures have been revised to reflect both the modification and the operating philosophy.

.. . . 4 , During a routine, unannounced inspection of plant operations conducted by the NRC resident inspector frem October 31, 1980 through November 26, 1980 (Report ' No. 50-293/80-30 pertains), the inspector reviewed Pilgrim Design Change Report (PDCR) 80-33 and the associated maintenance requests and determined that only six of the eight 20 inch containment vent and purge valves had been modified. No records were located that indicated the two outboard 20 inch ' purge inlet valves (A050358 and A050368) had been modified. , b 4 I I , l h , 1 l l l > .- -. . . - - . . - -, . , - . . - . . - . - . , _ . . - . . . - , . . . - . , . - . .

.. . . 5 IV. DETAILS A. Review of Pilgrim Design- Change Report (PDCR 80-33) and Associated Maintenance Request This document, entitled, Modification ~of Purge and Vent Valves to Prevent Opening i' ore Than 45 Degrees was reviewed and approved on May 13, 1980 by Mr. Jay .5 eyer, Senior Mechanical Engineer (Operations Support Depart- ment) following telephone discussion with Mr. Edward Ziemianski, the then Plant Support Group Leader. The modifications were effected by installing ~ threaded rods in the actuator to prevent full travel. Engineering and installing costs related to the modifications were estimated at $1,000 and no additional maintenance was required as a result of the modifications. The PDCR identified six (6) valves to be modified. These valves were identified as: A0-5044-A A0-5044-8 A0-5042-A A0-5042-B A0-5035-A A0-5036-A The modifications were initiated and completed on May 14, 1980 by the plant maintenance staff. There is no discussion in the PDCR relative to . the remaining two valves (outboard valves in the drywell purge inlet and the torus purge inlet). The PDCR and related Maintenance Requests are ' appended to this report as Exhibit 1. l l l , l , V- L '

-. . . . 6 B. Interview of Mr. Jack-Fulton, Acting Licensing Group Leader by NRC Investigators on February 24, 1981 Mr. Fulton stated he prepared letter 80-95 for signature based on input from the plant operating committee and the corporate engineering committee. Mr. Fulton acknowledged, that while the wording of the letter may have led to confus'a.1, the intent of the letter was to reflect that those valves that aie or could be opened during power operations were modified as stated in letter 80-95 to meet the interim commitment requirement. He .said, that based on the plant operating committee's input, it is his - understanding that the two valves in question are never open during power operation and for that reason they were not modified. . ! l l l l l l l L. -. , . . - - . _ . - - . --_ , . , _ . - - . , __ _ .. _ _ _ , _ . _ . _ , . . _ , , - _ _ _ _ _

. 7 . C. Interview of Mr. Jay Thayer, Senior Mechanical Engineer (Operations Support Department) by NRC Investigators on February 24, 1981 Mr. Thayer stated he worked with Mr. Hugh O'Connor, Principal Engineer, Corporate Nuclear Engineering, to gather and confirm input from the plant operations department to determine what was required to meet the modifi- cation commitment. He said he would also have reviewed BEC0 letter 80-95 after it was prepared by Mr. Fulton and that the preparation and input was based primarily on information from Mr. O'Connor. Thayer said he recalled having contact with the then Station Manager, Mr. Paul Maguire, who gave him the information regarding the six valves for modification. He said they also examined a P&ID to determine valve lineup when critical and at that time confirmed that the two outboard inlet valves in question were never opened for purging during power operations and were therefore excluded from the modification package. . _ r w=-c- w-- -- -,.- w - +,-w w- r w-w

_ __ _ _. . . . . 8 D. Interview of Mr. Hugh O'Connor, Principal Engineer, Mechanical Section, Nuclear Engineering, by NRC Investigators on February 24, 1981 Mr. O'Connor confirmed that he wrote the technical evaluation for the modification of the valve positions. O'Conncc advised that when the PDCR was originally written it included the two outboard purge inlet valves in the modification pack.tge. He said during interface with the plant operating personnel he was advised that the two valves in question were never opened for venting during power operations and therefore would not need to be modified. Mr. O'Connor said that to the best of his recollection he received that information from a performance engineer identified as I Mr. John Conlon. In any case, O'Connor,said upon examination, he was in agreement with the position that they were not opened and did not need modification. O'Connor said his fermal input to the preparation of the PDCR then reflected modification for only the remaining six 20 inch purge and vent valves. . , ! ! - .i . i a > ..--r-. _- ~ _ . . , . . _ . , , .

. - . _ . . . . . - . - - . -_ - -__- . . . , 9 ! - E. Interview of Mr. Edward Ziemianski, Management Services Group Leaier by NRC Investigators on February 24, 1981 Mr. Ziemianski said at the time this document was prepared he was the ' Plant Support Group Leader and was assigned to coordinate with corporate engineering the data for the PDCR modification package. Ziemianski stated that t h se two valves (A05358 and A05368) were not modified because the station operating procedures prohibitea the opening of those two , l valves from purging during power operations and it was his opinion that for this reason there was no need to modify the valves. ' i , ' ' , . . I I < < l

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_ - . . 10 F. Interview of Mr. John Michael Conlon, Performance Engineer (STA) by NRC Investigators on February 25, 1981 Mr. Conlon advised his involvement in the valve modification was primarily limited to personally going into the plant and identifying the valves by number and location and in preparing the maintenance work request in i order to expedite the modifications prior to startup. While not specifically remembering a discussion with Mr. O'Connor, he acknowledged that he (O'Connor) would have been the individual he most likely spoke with regarding the valve modifications and he may very well have discussed with him the fact that the outboard purge inlet valves were never opened during power operations. Conlon concluded that there would have been absolutely no reason to intentionally mislead anyone regarding the status of these two valves in that the modifications to the valves could have been completed in less than an hour without affecting plant operations if it had been needed to meet the requirements of the commitment. l > I - l ! l ' __ . . . _ __. . .._, _ __ __ . . _ .

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G. Interview of Mr. Charles Mathis, Deputy Nuclear Operations fianager and Acting Chief Operating Engineer by_NRC Investigators en February 25, 1981 ' Mr. Mathis advised that he was r.ot involved in the modifications to the 20 inch butterfly valves but he confirmed that the valves in question are not open for purging during power operations. He said at one time, Technical Specifications permitted these valves to be opened for inerting 24 hours after startup and deinerting 24 hours prior to shutdown. However, Mathis advised that in order to meet the 90 hour per year purge limit, Rev. 19 of Procedure 2.1.5 (Controlled Shutdown) was changed on September 12, 1979 to limit purging of the drywall until after the reactor is scrammed except by the standby gas treatment system (2 inch valves). Mathis provided a copy of Pilgrim Procedura. Change Notice (PCN 3481) (Exhibit 2 pertains) which reflected that the operating procedures for inerting and deinerting primary containment through the 20 inch valves was in fact changed on September 12, 1979 which is approximately 8 months prior to the submission of the modification report of the 20 inch valves. INVESTIGATOR'S NOTE The revised operating procedure including PCN 3481 was reviewed by ' the investigators confirming Mr. Mathis's information provided ' supra.

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. 12 H. STATUS OF INVESTIGATION This investigation is being submitted in a CLOSED status. > l O l l l l l t l i , l

. . 13 EXHIBITS 1. Pilgrim Design Change Report (PDCR 80-33) 2. Pilgrim Procedural Lnange Notice (PCN 3481) .

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/ U reviewed Safetv Question [ iYe i y.j; J Ne ! [ Recc= mended to the St.atic: Manager ,0 ~ . H ld W Date - e' ~ d ORC e-retarv / ' /. [ /) Date d/ Appr$vedforI=ple=entation - . ' 5:a:":.o: nahiger s PDCE Package Issued for Constructic: F -b #U/ ~ ' Date e/S h . M,C &' T Group ' / / r A' A / ._ - I=ple=entation Phase Cc=pletedW M[ [.dxcN/d Date 3[//v/ov / Cog'ai ant I ple6enting': diVidual - / / g/ / __ Date T// $6 PDCR Package Ready for Close-Ou: . As Lyned Individua .m x / '/ \\ & s- vl Date / / i. ' eb / fleu , Close-Out Package Reviewed , .. y Cog'aixas: Chief Es p '_:h) / / Ccc=ents: jij f 'S : 55 d < d 50 tc Se-l~ fikt ( 3 giQ

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095d!% MDQE 71+AN 4-C T0: Nuclear Operations Manager Reference: N0D 79- A / Discussion: The design documents for PDCR No. 80-?3 are hereby transmitted to the NOD for processing. The documents have been: ( ) Otiginated ( Verified and/or ( approved . ~ by the hTD.

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i - SAFETY EVALUATION ,t , , PILGRIM NUCLEAR POWER STATION - UNIT (1) '

SAFETY EVALUATION SERIAL NUMBER: l007(2) DATE: 5 Gf O(3) - . -v ' PROPOSED DESIdN CHANGE: (4) Por stops is poc em /vowT , sot.ar,cu vacve s . TO PREVEm TH EM f~Ane DPENinG Mo46 TifAN 4-5 t INITIATED BY: (S)ItWO b ,iv DEPARTMENT AND GROUP: M E~D (6) DESCRIPTION OF CHANGE: (7) Pur toucrea stoP me Bocr droor o^l SPA WG C11.un bsp of Mw Arap . SAFETY EVALUATION (8) The propased change, test or experiment: 1. ( ) Does (V) Does not increase the probability of occurrence or consequences of an accident or malfunction of equipment important to safety prpviously evaluated in the FSAR. 2. ( ) Does (V) Does not increase the possibility for accident or malfunction of a different type than any evaluated previously in

the FSAR. 3. ( ) Does (d Does not decrease the margin of safety as defined in the basis for any technical specification. SAFETY EVALUATION BASIS: (9) S tMCCE S PRr MG AeTvATET TO CLEW VALvG MD PrA CYLovDEA w 03rb e ??hj 90s m u rer, ec' rete tins v2 d V2 opett O BY TW Lw &EA S Nl 70 fCMA7i%%D!T W5 Kb A ffec7 od l'iWcro cov i iv G bF TH E JA L'CIE 'o 9 HO:sMG net 4 Sk~h=7 T RELAT'Eb CMM . . Exhibit 3.07-A (Sheet 1 of 2) 3.07-6 Rev. 0 exhibit 1 Page 4 .. . . . . . . . . . . , , . .

.- - .-. - - - I . ~ . . . APPROVAL ACTION 4 ' A. Approval of the proposed design change is: ( recoamended ?. ( ) not recommended. M O L (10) E r3.ro

.w ' ,, *,v ., Cogilizant Engineer /Date -

' . . , B: ' _ ( This change does not involve a change in the Technical Specifications. (). This change does not involve an unreviewed safety question as defined in 10CFR, Part 50.59 (C). () This change involves an unreviewed safety question as defined in 10CFR, Part 50.59 (C) and a request for authorization of this change will be filed with the Directorate of Licensing, NRC. (I Reportable Item (10CFR, Part 50.59 (b)). () Comments: , . . The proposed design change is: [) approved ( ) disapproved (12) M- !

(11) . Discipline Group / Leader /Date Discipline Group Leader /Date ' C, :, , , ORC CONCURRENCE REVIEW: l By Date: I . t l By Date: ! By Date: By Date: Exhibit 3.07-A (Sheet 2 of 2) 3.07-7 Rev. 0 Exhibit 1 Page 5 . . . _ . _ - . . -- . .. - - . . . - = . . - .

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wa6 . '*A '* .. ., - . PDCR 80-33 NARRATIVE MODIFICATION OF CONTAINMENT PURGE AND VENT VALVES COWsT8UWiON . - ....e..- + . .. , A. DESCRIPTION OF CHANGE The containment purge and vent system utilizes several 20" Rockwell Due to Butterfly Valves equipped with GH-BETTIS Robotarm actuators.. recent concerns regarding valve closure time and integrity immediately following a LOCA these valves must be modified to limit travel to the This change will allaviate the concerns mentioned 0-45 open positions. These if these normally closed valves are open concurrent v!.th a LOCA. valves are allowed- to be open during power operation by Tech. Specs. and operating procedures for only 24 hours immediately following a startup and for 24 hours preceeding a shutdown. B. COST-BENEFIT-EFFECT ANALYSIS 1. Reason for the change Recent NRC concerns have prompted reviews of the ability of the cor.- This tainment purge and vent system to isolate following a LOCA. isplation is necessary because even though the purge and vent system is used very rarely during power operation a minute possibility exfsts To min- that the system would be open to the containment atmosphere. " imize the dynamic effects of the high energy containment atmosphere during the closing of these valves, they will be mechanically limited to 450 travel or approximately half open. This will be done using a threaded rod to limit spring travel of the actuator. (See Figure 1) 2. Costs / Bill of material i a. materials: 3' - 1" steel rod b. engineering costs: $500. c. installation costs: 0500. 3. Anticipated Maintenante No additional maintenance will be required on chese actuators as a j result of this change. ' l f C. GOVERNING DOCUMENTS

= None . D. REFERENCE DOCUMENTS - 1. Drawing No. M-119-6-5 2. Drawing No. M-119-1-2 Exhibit 1 page 6 l - i .- _. _ _ __ _ _ --. .

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, . , E. SYSTD! REQUIRDIENTS full The threaded rods which will be installed in the actuators to prevent travel wil'_ % fabricated in accordance with Figure 1 (attached) . Fabrica- tior, detailsd re not important; however, the 5-7/8" length dimension is 'cra.tical -ind' [eterminetvalve position. This rod is installed in place of ' The valve an existing plug in the actuator designed for *.his purpose. , should be in the fully closed position during installation. This modifica- tion will not change or alter the position of the valve or the ".ntegrity or leak cightness of the valve pressure boundary. . F. ANALYSIS OF DESIGN ADEQUACY The design for this stop rod was transmitted via telecon by the actuator manufacturer GH-Bettis Company on May 13, 1980. . G. INDUSTRIAL HAZARDS l There are no unique industrial hazards involved with this modification. H. INSTALLATION INSTRUCTIONS 1. Fabricate six (6) stop rods in accordance with Figure 1, 2. Remove plug on spring cylinder of actuator and screw in stop rod on the following valves: Ccmplete ,

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. E C.. aim . Exhibit 1 Page 9 P00R BRIGl%I. "

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8 E.Co. Form X5259 ' Exhibit 1 Page 10 ! , . i U l

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cf.m ALL WORK COMPLETE SY 'j COMPLETED tv / TECHNICAL SPECIFICATION OPERASILITY TESTING - NOT REQUIRED QF%6S M^ j R EcuiR EDJ(- DEsCR:rfiONiPROC. RO. .f . . g iSOLAflO%$/ RED T AGS REMOVEDhST T AGS APPLIED O ,/b s N^ i* ] TIME /OATE . Oz TE$ TING $ ATISF ACTORiLY CCMPLETED ANO TEST TAGS REuOVLO - Sy K 8 D ALL QUALITY CONTROL REOUIREMENTS MET - APPROVED BY OC #(k R LQG A'ND FILES UPDATED AND THE $YS.EM/EOuiPMENT MAS *EEN ALL T AG$dSOLATIONS REMOV ED. ACCEPT ANCE CRITERI A ET h,I ,D OPER.$UPVR. - l RETURNED TO NORMAL TruE/DATE 71 in - O ORIGIN ATOR-WE-CO E- CME-M/S ECTV-M5E-O$-MR-4N-PROC.-FiL E 6 OS $7ATION FILE h;

8 E.Co. Form x5259 Exhibit -1 Page 11 ~ , i 4

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  • 4

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Mb (NED Group Leader)/Date gg9%(NED d/ 7I&ngineer)r/D/te / /C gniza t / Design hppr va .r/q [ ( 0 !C ' _ ORC) Reviewed by _ ( 7 viewed by ! Revie<ed in ORC Meeting No. _ _ Date DRC Chairman's Approval Rev. 3- 3.03-8

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PNPS OPERATIONS MANUAL

.(gj PROCEDURE CHANGE NOTICE ' "uate ff /d /19 - PCN NO, s ^/ 7 / 2 . /. s . / , - ' bo d //eM dAuh b Procedure No. Of 68 6 Title ~ Ilew Temporary ~ Design LPtocedural Reason g For JProcedure Procedure ._ , Change V Revision @ PCN lSRO Permanent Change Desired -

,JChange SRQ No. Oyes O No (expiration date ) . '(Su"Lary of r ason for lc ange) ff [k o 2, , 2LL w2 e % u w, aw n - - U 6 PCN Initiated Requested Revision Other Known by 8. f C Reviewed by Procedures Affected - LisA of Effected Pages with existing Rev. Nos. L h /) ~ %. /tE. & 5 .'~ f w t /dA k A 0 l 4 2l C ' - V O 90 SAFETY EVALUATION complete Section A or B below) d

  • Safety Evaluatj

4y -% A.- A w u e.on Bals : ' x 7- x , ax e.> m ca1r ~ ~ ~, zAJ A LM / / d % Therefore the proposed procedure or cliange: ( ) DOES Increase the probability of occurrence or consequences of an accident or malfunction of equipment important to safety pre- ( OES viously evaluated in the Final Safety Analysis Report. NOT ( ) DOES Create the possibility of an accident or malfunction of a different type than any evaluated previously in the Final , ( DOES Safety Analysis Report. 'NOT .. (. ) DOES Reduce the margin of safety as defined in the basis for ( ' NOT DOES any technical specification. - . Reference Material: - , l B. Safety Evaluation was performed in accordance with procedure 1.3.23 Number ___ REVIEW Th2 ebove listed procedure revision, safety evaluation, and PCN have been reviewed cud are acceptable for approval by the Station Manager. ff Rtviewed by d [ (ORC) Date 9/.7/79 Reviewed (ORC D* (N2 /i 'iisionreviewedinORCMeeting#/b'M {[ fi ! tu stionManager'sApproval.d b ' xe Da / /74 ' ~ hl - Exhi61't 2 1.3.4.A-1 Rev. 14 ~ _ 4 }}

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