IR 05000338/1990016

Insp Repts 50-338/90-16 & 50-339/90-16 on 900709-13.No Violations or Deviations Noted.Major Areas Inspected: Surveillance Testing of Main Steam Safety Relief Valves & Follow Up of Licensee Actions on Previous Insp Findings

ML20058P890
Person / Time
Site:	North Anna
Issue date:	08/02/1990
From:	Belisle G, Lenahan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20058P889	List: IR 05000338/1990016 ML20058P884
References
50-338-90-16, 50-339-90-16, NUDOCS 9008210007
Download: ML20058P890 (7)

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0 H1 ' UNITED STATES

/ 9q'o{ NUCLEAR REGULATORY COMMisslON

[* [o REGION 11 -

5' y 101 MARIETTA STREET. i

• * ATLANTA. GEORGI A 30323

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Report Nos.:

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50-338/90-16 and 50-339/90-16 l

Licensee: Virginia Electric and' Power. Compan Glen Allen, VA .23060 Docket Hos': . 50-338~and 50-339 License Nos.: NPF-4 and NPF-7

Facility Name: North Anna 1 and 2 Inspection Conducted: July 9-1 .1990 Inspector: 8/I/fo J. J. Lenahy(/ Date Signed, Approved by: - V H td (f 0 G. A. Beli-le, Chief " Date Signed Test Programs Section Engineering Branch Division of Reactor Safety-SUMMAR Scope:

This routine, unannounced inspection was conducted in the areas of surveillance-testing of the main steam safety relief = valves and follow-up of licensee's-actions on previous inspection finding Results:

The licensee has been responsive- to NRC' concerns regardingi the snubber surveillance progra The licensee's corrective actions' appears..to be

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technically sound and thorough and previously' identified problems have been resolve In the areas inspected, violations or deviations were not' identifie PDR ADOCK 03000338 Q PDC l

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{ 'y REPORT. DETAILS .

, Persons' Contacted- .

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' Licensee Employees .

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• Bowling,' Assistant Station Manager.

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• Compton, Supervisor . Inservice Inspection / Nondestructive Examination (ISI/NDE)andEngineeringProgram

• P. Kemp Supervisor, Licensing

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( J. Wroniewilz, Assistant Superintendent, Station Engineering

• C. Zalesiak, Lead Civil Engineer, Station Engineering Other- licensee employees contacted during this inspection included-engineers, technicians and administrative personnel.- ' t-NRC Resident Inspectors

• Lesser,' Senior Resident Inspector

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L. King..- Resident Inspection

• Attended exit interview Main Steam Safety Relief Valve Setpoint Testing --Units 1 and 2'(61701)' ;

The inspector reviewed results of setpoint testing of the ' main ' steam -

safety relief valves (SRVs) ~and verified compliance with Technical- - ,

Specifications (TS) 4.0.5 and 3/4.7.1.1,. The inspector examined periodi .

test procedures 1-PT-70 and= 2-PT-70, Main Steam Code Safety _ Valve Setpoint:

Verifications. These procedures contain requirements' for- test initial conditions, test instructions, and acceptance criteria. _ 'The procedures i provide instructions for performingy the , setpoint testing onsite, J or: j shipping the SRVs offsite for' vendor testing. ' During.. refueling outages, !

all 15 SRVs are normally removed from each unit and.sent to an offsite vendor, Wyle Laboratories, for testin Five of the fifteen Unit 2-SRVs, which were tested in March '1989 and six l of the fifteen Unit 1 SRVs, which were tested in'May~1989 had "as-found" setpoints outside the TS limit The licensee: reported- these ~discre- 1 pancies to the NRC in Unit 2 Licensee Event Report '(LER) 339/89-005 onL April 12, 1989, and in Unit 1 LER 338/89-009 on June-13, 1989.< Following >

the as-found setpoint' tests,- all 30 SRVs- (15 from each unit) exhibited '

disc to seat leakage. The valves were' refurbished, adjusted, and retested to ensure the set pressures.were within the allowable TS' limits. Thej following is a ' summary of the "as-found" SRV set point test- results for .

both units: '

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TS Setpoint Value -

Valve Number * Range In PSIG As-found Value (psig)**

MS101A 1074-1096 1091 MS101B- 1074-1096 1069 i

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MS101C 1074-1096~ 1094:

Mst9PA 1084-1106 1076 MS102B 1084-1106- 1063 MS102C 1084-1106 1082'

MS103A 1099-1121 1113 ,

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-MS103B- 1099-1121 1087 MS103C 1 1099-1121- 1119'

MS104A 1109-113 MS104B 1109-1131~ 1119 MS104C 1109-1131 1107

.MS105 MS105B 1124-1146 1135 MS105C . 1124-1146 1133

.MS201A 1074-1096 1081 MS2018 1074-1096 1076 MS201 MS202A 1084-1106 1137 MS202B 1084-1106 1091

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MS202C 1084-1106 1088 MS203A 1099-1121 .1154 MS203 MS203C 1099-1121 -1112 ,

MS204A 1109-1131 1111 MS204B 1109-1131 1101 MS204C 1109-1131 1131-MS205A 1124-1146 -113 MS205B 1124-1146 -1134 i MS205C 1124-1146 1116'

• Unit I valve numbers are those in 100 series, e.g., MS101, MS102 1 Unit 2 valve numbers are those in 200' series, e.g., MS201, MS202-

• • The "as-found" values are for the initial lift of three test run The- licensee is currently performing an evaluation to determine if .the - "

tolerance _for the SRVs can be increased from plus or minus one percent.to plus or minus three percen If the additional tolerance can b justified, a. Technical Specif! cation change will be requested. The above setpointf test results are typi:al' of those 'found throughout the industry,

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i Within the areas inspected, no violations or deviations-were identifie . Onsite Follow-up of Written Reports to Non-routine Events >at Power Reactor Facilities (92700) j i

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(Closed) Licensee ' Event Report (338/89-09):- Main Steam Safety Valve -

Setpoints Out of Tolerance. The problem identified by. this LER is discussed in paragraph 2 abov The six Unit-1 SRVs which had >as-found" setpoints outside the TS limits were approximately one-half of one percent-below the TS limits. This had no safety significance because having

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slightly low setpoints would not have prevented the SRVs from performing -

their safety functio ; Action on Previous Inspection Findings (92701 and 92702) , (Closed) Unresolved Item (338,339/88-12-01), Evaluation of Snubber i'

Visual Inspection Failures-In a letter to the NRC dated . August 22, 1988, Serial No.88-487, Subject: North Anna Units 1 and 2 Snubber Visual Inspections, the licensee discussed their evaluations of snubber visual inspection:

failures which occurred during the Unit 1 1987 'and. Unit 2.1986 refueling outages. The licensee also submitted a copy'of Inservice Inspection Procedure ISI 3.0, Safety-Related Snubbers, which was

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revised as a result of .this Unresolved Item to clarify the definition '

of visual inspection failure The inspector examined procedure  !

ISI 3.0 and noted that methods for evaluating visual inspection ,

failures were clearly defined. The inspector also noted that the i procedure includes examples of snubber visual inspection failures.

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which were considered .to be a result of transients, isolated damage, or other random events per TS 4.7.10.b.- The licensee's' August 22,

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1988, letter discusses their evaluation of the causes' of the  ;

visual inspection failur These failures were attributed to be maintenance related and not generi In addition, two of the snubber ;

visual inspection failures, one from 1each unit involved loose connections on hydraulic fluid lines between' the' steam generator snubbers and the external common reservoirs. TheseLsnubbers were replaced during the 1989 refueling outages with snubbers' which have -

an internal reservoir. Based on review of the' licensee's evaluation of the previously identified visual inspection failures, and revisions to procedure ISI 3.0, Unresolved Item 338,339/88-12-01 is close (Closed) Unresolved Item (338,339/88-12-02): Preventive. Maintenance '

Program for Correction of Fluid Leaks in Unit 1 Hydraulic' Snubbers

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During ' visual inspections. conducted in 1987,. low fluid lev.els 'were identified by the licentee -in several snubbers installed in Unit The licensee investigated this problem and was unable to ascertai '

the cause. However, none of the snubbers were considered to be inoperable. The licensee reviewed their maintenance practices and- i concluded that their maintenance program was adequat The inspector examined procedure number MMP-C-HSS-1 Mechanica Maintenance Procedure for Repair and Pre-installation Testing 'o Grinnel Snubber Cylinders and Valve Blocks. This procedure provides'

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instructions for repair rebuilding, and pre-installation testing of i all hydraulic: (Grinnel), snubbers- installed in both units with the  :

- exception of the- steam generator (Taylor) . snubbers which are-maintained by.an offsite vendo Review'of procedure MMP-C-HSS-1 disclosed that the licensee's snubber ,

rebuilding: program includes replacement of; all' seals, replacement of ,

the lexan reservoir, replacement of the lock-up barrel springs, and a *

complete visual inspection of all other parts for defects prior toL rebuildin All snubbers--are -functionally tested following completion of rebuildin The inspector discussed the snubber rebuilding program with licensee ISI engineers and the snubber mechanics. These discussions disclosed  ;

that- the licenses currently rebuilds one-third of .their snubbers

during each refueling outage.: -This program is based on a snubber scsl service life of five year The snubbers are functionally #

tested befcre rebuilding. The' purpose .of the functional , testing is'

to establ'.sh that the snubbers were operable prior to removal, and to:

establish a data base. to justify. extending the snubberc seal service  ;

life to seven year The inspector examined'the results of visual inspections performed on Unit 1 inaccessible snubbers"in :May - June and December 1989 and on Unit 2 inaccessible snubbers in February and March 198 Two visually inoperable snubbers were identified during the May - June-1989 Unit i visual inspection. One of these-inoperable snubbers was fabricated by Grinnel which had a cracked lexan reservoir. - The remaining was a steam generator snubber' with. an empty remote

,_ reservoir. The steam generator snubbers .were1 removed and replaced j with new Taylor snubbers with! internal reservoirs. 0ne visually:

inoperable snubber was . identified during theJDecember Unit-1 visual inspectio This was , one of a the . new, Taylor Jmodels, - Serial Number 005, installed on support number 1-RC-SF-HSS-1A, This snubber g I had zero fluid - pressure in the internal : reservoir. Normally, the L

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l internal. fluid reservoir is: pressurized to 2000 psig. .The. snubber l- was replaced with a spare and sent offsite to Wylie Laboratories for a E testing and repair. -When tested in the'"as-found"' condition, with '

zero internal fluid- pressure, the snubber passed the initial i

functional test. The test' data indicated -that the snubber' had ' -f

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sufficient fluid to . perform its, function ~ even though - the fluid . y pressure was zer However, the' snubber was disassembled, inspecte .

rebuilt and - retested prior to return to' the site. for possible 'l reinstallation. All Unit 2.~ snubbers .were found ' to be : acceptable during the 1987 visual inspectio Based on the visual inspection results, the current inspection

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l interval is 12 months for Unit'1~ inaccessible snubbers and.18 months ,

for Unit 2 inaccessible snubbers. The inspector also. examined the l results of functional tests performed on Unit:2 snubbers in March -  ;

! April 1989 and on Unit I snubbers in May June 1989. - - All Unit ~2- '

snubbers tested met the functional testing acceptance criteria, while-two of the Unit I snubbers had results which.were slightly outside the functional test acceptance criteria.-

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l 5 r c. (Closed) Violation (338,339/90-02-01):

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IST Program Deficiencies The licensee's corrective actions, for this- violation are stated in l

their April 2,- 1990, response to NR The licensee developed test i procedures to include inservice testing (IST) of the specific valves L cited in the -violation.. The licensee also performed an- overall-evaluation of their IST: program to determine if any other valves -

should be included. The results of this review and any justification for not testing were included in Revision 6 to the licensee's Pump !

and Valve IST program. The program has been submitted to the NRC and is currently being reviewe ~

l The. inspector examined the Periodic Test (PT) procedures _which have-been implemented to include testing of service water valves which had ;

not been included in Revision 5 to their IST program. The-inspector also' reviewed the results of the-completed. PT The test dates are noted in parenthesis after the procedure titl The following -

procedures were examined:  ;

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1-PT-213.2A.1, Valve Inservice Inspection for SW Check Valves to 1-CH-P-1A Lube Oil, Seal, and Gear Box' Coolers L(May 10,1990) i l

l - 1-PT-213.28.1, Valve ISI for SW Check Valves to 1-CH-P-1B Lube l Oil, Seals, and Gear Box Coolers (April-20, 1990);

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1-PT-213.20.1 - Valve ISI for SW Check Valves to 1-CH-P-1C Lube Oil, Seals, and Gear Box Coolers (April'20, 1990)

- 2-PT-213.2A.1, Valve:ISI for-SW Check -Valves to 2-CH-P-1A Lube 1 Oil, Seals, and Gear Box Coolers-(April:24, 1990)  !

l 2-PT-213.2B.1, Valve ISI for SW Check , Valves to 2-CH-P-1B- Lube

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011, Seals, and Gear Box Coolers'(May 18,1990).

- 2-PT-213.2C.1, Valve ISI for SW Check Valves to 2-CH-P-1C Lube ,

i 011 Seals and Gear Box Coolers (May 14,1990)' 4

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1-PT-75.2A, Service Water Pump 1-SW-P-1A Test (April 22,1990)=

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1-PT-75.2B,ServiceWaterPump1-SW-P-1BTest(April' 22,1990)

d. (Closed)IFI(338,339/90-12-01): Pressurizer Oven Seismic- Analysis-The inspector reviewed Design Change Packages (DCP) 84-69 and 84-70, Pressurizer Safety Valve Loop Seal Installation. DCP 84-69 applies to Unit.1 and DCP -84-70 applies to Unit Revision 9 to DCP 84-69 and Revision 5 to DCP 84-70 were written to -

resolve deficiencies identified in 1989 with the original pressurizer loop seal ovens installed ' in 198 These deficiencies were documented on Deviation Report Numbers DR 87-1266 and DR 87-140 <

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The licensee addressed previous ^ concerns involving damage to other

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safety-related equipment resulting from a failure of the pressurizer ovens in Technical Report No. CE-010. . The inspector examined Technical Report CE-010; DR 87-1266; DR 87-1400; drawing numbers N-8469-1-V-801, Sheets 1 through 11, Pressurizer Loop Seal . Insula-. -3 tion; DR 89-1077, which was written to resolve IFI 338,339/. -

90-12-01 (previously IFI- 338/89-200-01).- and ' a memorandum from-R. W. Riley to M. W. Gettler, dated November 10, 1989, Subject: ,

Final Close-out Analysis DR 89-1077, Pressurizer Safety and Relief ,

Valve Projec !

!' Exit Interview The inspection scope and results were summarized on July 13, 1990, with ,

those persons indicated in paragraph 1. . The inspectors described the areas inspected and discussed in detail the inspection result Proprietary information is not contained in this report; -Dissenting- t comments were not received from the license Licensee Management was informed that the following items were closed:

LER 338/89-09, Paragraph 3 URI 338,339/88-12-01, Paragraph URI 338/88-12-02, Paragraph Violation 338,339/90-02-01, Paragraph IFI-338,339/90-12-01, Paragraph t q

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