IR 05000211/2003004

Insp Repts 50-280/85-07 & 50-281/85-07 on 850211-0304. Violation Noted:Charging Pump Intermediate Seal Coolers Not Operating in Accordance W/Tech Spec 3.13.B.3-Paragraph 5.d

ML20127J500
Person / Time
Site:	Surry, 05000211
Issue date:	04/17/1985
From:	Burke D, Marlone Davis, Elrod S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20127J160	List: IR 05000211/2003004 ML20127J156 ML20127J179
References
50-280-85-07, 50-280-85-7, 50-281-85-07, 50-281-85-7, NUDOCS 8505210481
Download: ML20127J500 (7)

Text

pnmtro UNITED STATES p ^o NUCLEAR REGULATORY COMMISSION p

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, ^ REHION il g j 101 MARIETTA STREET, * ATLANTA, GEORGI A 30323

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Report Nos.: 50-280/85-07 and 50-281/85-07

. Licensee: Virginia Electric and Power Company Richmond, VA 28261 '

Docket Nos.: 50-280 and 50-281 License Nos.: DPR-32 and DPR-37 Fac'ility Name: Surry I and 2 Inspection Conducted: February 11 - March 4,1985 Inspectors: '~fYw/ W M .2/#/4rcM18l26 Date Signed D./. Burke,'Se'niorRp41dentInspectp TJML M/J. Davis,~ Res den nspector

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~Date Signed Approved by: /

S. Eliod, Section Chief

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' Dat6 Signed

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Division of Reactor Projects SUMMARY Scope: This routine, unannounced inspection entailed 150 inspector-hours on site in the areas of plant operations and operating records, plant maintenance and surveillance, plant security, followup of events, licensee action on previous enforcement actions, and licensee event report Result: In the areas inspected, one violation was identified in the area of plant operations; Unit 2 charging pump intermediate seal coolers not operating _in-accordance with Technical Specification (TS) 3.13.B.3 paragraph e 8505210481 850429 PDR ADOCK 05000280 G PDR

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REPORT DETAILS Persons Contacted Licensee Employees R. F. Saunders, Station Manager D. L. Benson, Assistant Station Manager H. L. Miller, Assistant Station Manager D. A. Christian, Superintendent of Operations E. S. Grecheck,_ Superintendent of Technical Services H. W. Kibler, Superintendent of Maintenance D. Rickeard, Supervisor, Safety Engineering Staff S. Sarver, Superintendent of Health Physics R. Johnson, 0perations Supervisor R. Driscoll, Site QA Manager-W. R. Runner,oSupervisor, Administrative Services Other licensee employees contacted included control room operators, shift technical advisors (STAS), shift supervisors, chemistry, health physics, plant maintenance, security, engineering, administrative, records,- and contractor personnel and supervisor . Exit Interview The inspection scope and findings were summarized on a biweekly basis with certain individuals in paragraph 1 above. The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspectio . Licensee Action on Previous Enforcement Matters (Closed) - Violation (281/84-10-01), Reactor Coolant System (RCS)

cooldown rate exceeded the 50 degrees F/hr limit of TS 3.1. Appropriate retraining and. instructions have been provided on this even (Closed) - Violation (280, 281/84-15-01), Failure to follow Fire Protection procedures- Administrative procedures were strengthened and

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personnel reinstructed to ensure complianc (Closed) - Violation (280, 281/84-15-02), Inadequate periodic testing and post-maintenance testing procedures. The procedures have been revised and the program strengthened; smoke and heat detectors are being specifically identifie .

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2 (C1'osed) - Violation -(281/84-20-01), Inadequate maintenance procedures for ' setting motor operated valve (MOV) torque switches. Procedures

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have been revis'ed to ensure proper torque . switch inspections : and settings (EMP-C-MOV-50). (Closed) -' Violation (280, 281/84-24-01), Written safety evaluation for

- modifying component cooling. water system (CCW) to reactor coolant. pump -

.(RCP) -thermal barriers, etc. as described in Final _ Safety Analysis Report (FSAR), not performed. The: evaluation was performed and docu-mented, .and determined that an unreviewed _ safety question does not exist. High pressure trip and check valves will be installed in the

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CCW system as described -_in the FSAR, during upcoming refueling' outage ' :(Closed) ~ -. Violation . (281/84-24-02), Electrical maintenance procedure

= EMP-C-RT-24 not properly followed. The procedure was revised and the violation reviewed with -electrical - department personnel, emphasizing the proper use of jumper ; _ Unresolved Items Unresolved items were not identified during this inspectio . -Operations:

' : Unit 1 an'd 2 were inspected and reviewed during the inspection' perio '

The inspectors routinely toured _the control room and other plant areas to verify that plant ' operations, testing, and maintenance were being-conducted in accordance with. the facility TSs and -procedures. .The inspectors verified that _ monitoring equipment ^was. . recording as'

required, equipment was. properly tagged, and plant housekeeping effo'rts

< were adequate. The inspectors also_ determined that appropriate radiation controls were properly established, . clean areas were being .

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controlled in accordance with procedures, excess material or equipment :

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L was stored properly, and combustible material and debris were disposed i

of expeditiousl During tours, the inspectors looked for .the f existence of unusual fluid leaks, piping vibrations, piping hanger and l: seismic restraint settings, various valve and breaker._ positions, equip-p ment' caution and danger tags, component positions, adequacy :-of . fire

fighting' equipment, and instrument calibration dates. Some tours were-

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l' conducted on backshifts. Inspections included areas in the Unit 1 and 2 cable, . vaults, switchgear rooms, control rooms, auxiliary building,

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and cable penetration areas to verify certain breaker and equipment

positions . for safety-related components. The _ inspectors routinely-L -conduct partial walkdowns of Emergency Core Cooling System (ECCS) and L ~ Engineered Safety Features (ESF) system During periodic stroke testing of the Unit 2 Service Water (SW) motor operated valves MOV-SW-203A through D, a report of service water

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spraying into the safeguards building containment spray pump room was-made. The event was repeated when MOV-SW-203A was subsequently stroked

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'T on March 4,.1985. The rapid flow of service water into the 36 inch SW

. Llines when the MOVs .are opened, apparently causes a momentary surge' of water into the SW vent line standpipes.which ventLinto the safeguards

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room, when the water . reaches the closed. valves MOV-SW-204A through Some ofz the vented-SW sprayed onto certain Containment Spray. System

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pump motors . and valves in the room. All .affected pumps were opera-

.tionally tested and-POVs stroked to verify operability; no ' problems were observed. . The licensee will redirect the vents or manually

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, 11solate.them during MOV testing to prevent recurrence. IFI (281/85-07-03.) Unit 1 and Unit 2 operated at power for the duration of the reporting period. No trips or shutdowns occurre On February 15, 1985, operations personnel discovered valve misalign-ment on the Unit :2 charging pump cooling water' subsystems. The sub-systems consist of two water systems, a-closed loop component cooling water:(CCW) system which cools two' seal coolers on each of the three charging. pumps, and a_ service water (SW) system which removes heat from-the- CCW system via the intermediate seal coolers or heat exchanger Service : water also -directly cools the charging pump lubricating' oil

. coolers on each charging pump. At 5:45 a.m. on February 15, 1985, service water pump 2-SW-P-10B was secured for. inspection and 2-SW-P-10A was placed into service;: two operations team members were ' directed to shift the SW and CCW subsystems.to the A intermediate seal cooler (ISC)

and verify valve positions. The individuals reported that the transfer to; A ISC was completed and-verified. Neither the operating procedures (2-0P-51.5 series) nor the valve checkoff '(alignment) procedures- were -

used although independent verification was required. During a routine valve alignment check at 9:30 p.m. on February 15, 1985, operations personnel discovered that CCW was isolated to the B -ISC, while SW was ,

isolated to the A ISC, rendering both Unit 2 ISC inoperable during power operation. This is a Eviolation - of TS 3.13.B.3, which requires

'that one charging pump ISC shall be operating:when the Unit is critical

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(281/85-07-01). The coolers were apparently valved out approximatel .7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. A similar event occurred on Unit 1-on May 18, 1984 (see Inspection. Report 50-280/84-17), however, a Notice of Violation was not issued in accordance with 10 CFR 2, Appendix C,'IV.A. During the time the coolers were valved out, no notable -increases in charging pump temperatures were observed due to ambient heat- losses -and the full

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' operability of the charging pump lubricating oil coolers, which remove about 75' percent of the heat load.(seal coolers remove 25 percent). A-subsequent engineering study determined that the charging pumps could operate under emergency or normal conditions for more than a . week without exceeding = any pump temperature limits. The intermediate seal 1 cooler valve alignments are inspected / verified weekly per valve checklist 2-C L-54. In ~ addition, ~the opposite unit charging pump cross-tie was .

available to supply Unit 2. The individuals involved were suspended for not utilizing the procedures, which appear adequat '

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The licensee identified an additional example of the violation

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(280/85-01-02), regarding the. implementation of TS Amendment 100 for-1 Unit Specifically, TS 4.1.B.S.a requires that each reactor -vessel head vent-path shall be demonstrated operable following each refueling

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by verifying that the upstream manual isolation valve in each vent _ path i s = locked - 'in the open position.. Although the Unit 1 vent valve

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=1-RC-602 was opened. and independently. verif_ied open, as : documente December 9, 1984, on the OP 5.1A checklist, the valve was not locked in j- lthe open position. The licensee will. include this item in the response

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'to (280/85-01-02) as discussed abov . Maintenance and Testing  !

, During routine stroke testing of Units 1 and 2 MOVs, the following MOVs did not' perform -satisfactorily:

MOV-SW-103c, torque'd out MOV-SW-2028, manual lever did not disengage

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MOV-SW-105C, did not close MOV-CS-200A,.did not open

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MOV-FW-151F, ' thermally overloaded - replaced breaker heater coil The MOVs ,were worked or manually stroked, and subsequently satis-factorily tested. ' The licensee agreed to perform a programmatic review

. of. safety-related MOVs during the upcoming outages. The review will:

include torque and limit switch inspections, breaker heater coil verifications and inspection of the manual tripper arms on certain s SMB-000 and -00. valves Open Item (281/85-07-02). .The inspe'ctors. reviewed the maintenance performed on the Units 1 and 2 Service Water (SW) flow-instrumentation. Some seaweed-type plugging

< was found in certain instrument tubing, and two of the pilot tubes had to be reoriented to perform properly. IFI (280/84-30-03) is. closed;

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periodic inspections and calibrations of the instruments are_ performed during outages.

The inspectors observed that all specified under-voltage trip actuator-(UVTA) modifications. appeared to be in place on the Unit l' trip breaker

- UVTAs. ~ Extensive testing and inspections continue to ' verify operabi-lity of' the components. - Open Item (280/84-17-01) is close The Westinghouse DB-50 shunt coil trip circuitry has also been installed

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and is tested as required on Units 1 an . LER Review The inspectors reviewed the Licensee Event Reports (LERs) listed below to l

' ascertain that NRC reporting requirements were being met and to determine the appropriateness of corrective action- taken and planned. Certain LERs '

were reviewed in greater detail to verify corrective action and determine

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compliance with TS and other regulatory requirements. The review included 2 examination. of logbooks, internal correspondence and records review of Site ,

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5-Nuclear Safety Operating Committee SNSOC meeting- minutes, and discussions with various staff members. Within the areas inspected, no violations were identifie (Closed) LER 280/85-002 concerned a reactor trip from 20 percent power caused by an operator's failure to adequately control steam generator level during transfer from bypass to the main feedwater regulating valve (Closed) LER ~ 281/85-01 concerned an inadvertent start of an auxiliary feedwater pump during monthly testing of reactor protection logic. Instru-ment technicians-failed to perform the test in the specified sequence. The test switch for the C steam generator low low level was actuated out of sequence in lieu.of the switch for pressurizer high pressure. The pump was stopped and the test suspended. Instrument technicians were made aware of-the importance of following procedure (Closed) LER 280/84-24 concerned a spurious safety injection (SI) which occurred while the unit was in a refueling shutdown with the core defuele The spurious SI was due to an inadequate procedure in that the procedure did not require the resetting of CLS-hi. Outstanding work procedures that required the de-energizing of CLS-hi were held in abeyance until the procedures could be modifie (Closed) LER 280/83-58 and 280/83-43 concerned malfunctioning main feedwater regulating valves that failed to fully close upon receipt of a RCS low Tave feedwater isolation signal following a reactor ~ tri The feedwater regulator valves were rebuilt during a subsequent outage, and are routinely teste (Closed) LER 280/83-03 concerned recirculation spray service water motor operated valve (MOV) failures on both Units. Operators continued to be assigned to monitor valve performance or operate the valves manually during emergency conditions. The valves are cycled on a quarterly basis. Larger valve operators have been installed on the Unit 1 valves and are to be installed on the Unit 2 valves during the upcoming outag (Closed) LER 281/83-46 concerned sheared operator mounting bolts on MOV-RS-255A (' A' outside recirculation spray pump suction valve). The one quarter inch diameter bolts used in the base were not of sufficient strength to support the shear forces encounterad when operating the valve. The valve motor operator support stands on both units now use six half inch diameter by seven inch long Hilti concrete anchor bolts to attach the stands to the concrete floo . Plant Physical Protection The inspectors verified the following by observation: Gates and doors in protected and vital area barriers were closed and locked when not attended.

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~ Isolation : zones described in- the physical security plans. were not compromised or obstructe c. : Personnel ~ were properly identified, searched, authorized, badged' and es'corted as necessary .or plant access-contro r C

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