IR 05000280/1979002
| ML18114A486 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/12/1979 |
| From: | Burke D, Cantrell F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18114A484 | List: |
| References | |
| 50-280-79-02, 50-280-79-2, 50-281-79-02, 50-281-79-2, NUDOCS 7905020019 | |
| Download: ML18114A486 (9) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30303 Report Nos.: 50-280/79-02 and 50-281/79-02 Licensee: Virginia Electric and Power Company P. 0. Box 26666 Richmond, Virginia 23261 Facility Name: Surry Power Station Docket Nos. : 50-280 and 50-281 License Nos.: DPR-32 and DPR-37 Inspection at Surry Site near Surry, Virginia Inspector: ~l ~tt:...a ~
D. J. Burke 1/?
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Approved by:
,4".!-i.,, u Date 1Signed s/;i/)0 F. S. Cantrell,
- Section Chief, RONS Branch
~ 1)ate7 Signed SUMMARY Inspection on January 2 - February 2, 1979 Areas Inspected This routine unannounced inspection involved 184 inspector-hours onsite in the areas of plant operations, followup of Licensee Event Reports and IE Circulars, plant physical protection barriers, preparations for Unit 2 steam generator replacement outage, and previously identified unresolved and open i terns.
Results Of the seven areas inspected, no apparent items of noncompliance or devia-tions were identified.
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DETAILS Persons Contacted Licensee Employees W. L. Stewart, Station Manager, 1/2/3/4/5 J. L. Wilson, Superintendent Operations, 1/2/3/4/5 R. F. Saunders, Superintendent, Maintenance, 1/2/3/4/5 T. A. Peebles, Superintendent, Technical Services, 2/3 G. E. Kane, Operating Supervisor R. L. Baldwin, Supervisor, Administrative Services, 5 C. F. Wheeler, Station Security Supervisor J. S. Fisher, Fire Marshall W. A. Thornton, Chemistry Supervisor F. L. Rentz, Resident QC Engineer, 1/2/3/4/5 R. G. Smith, Health Physics Supervisor D. A. Christian, Associate Engineer, 1/2 L. J. Curfman, Reactor Engineer W. C. Earl, Associate Engineer J. Pickworth, Senior Engineering Technician, QC D. H. Rickeard, Engineering Technician J. W. Martin, Jr., Supervisor, QA Operations** and Maintenance, 1/3/4 E. P. Dewandel, Administrative Assistant, 1/2/3/4/5 T. S. Kenny, Outage Coordinator - SCRP C. W. Rhodes, Resident Engineer, Construction - SCRP Other licensee employees contacted included technicians, operators, and office personne /
Denotes those present at the exit interview on January 5, 197 /
Denotes those present at the exit interview on January 12, 197 /
Denotes those present at the exit interview on January 19, 197 /
Denotes those present at the exit interview on January 26, 197 /
Denotes those present at the exit interview on February 2, 197 Exit Interview The inspection scope and findings were summarized on January 5, 12, 19, 26 and February 2, 1979 with those persons indicated in Paragraph 1 abov The resident reactor inspector also attended the Steam Generator Replacement Program briefing on January 8, 1979 and the exit interview of A. Herdt, J. Wilcox, and S. Elrod, Region II personnel, on January 19, 1979 and that of R. J. Hennessey and J. L. Skolds, Region II inspectors, on January 10 and February 1, 1979 respectivel During the February 2, 1979, interview, licensee management stated
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-2-that the Gaitronics telephone paging system provides the constant communications required under the "buddy system" described in T.S..B.1.f. The inspector stated that this matter is considered unresolved (see Paragraph 8.a).
The license conditions for the Surry Steam Generator Repair Program issued January 19, 1979 were also discusse.
Licensee Action on Previous Inspection Findings Unresolved Items (Closed) Unresolved Item (76-6/3): Technical Specification (TS)
changes regarding reactor coolant pump (RCP) supports. TS section 4.2 has been revised to accurately describe the methods of inspec-tion for the RCP supports and other component.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve noncompliance or deviation New unresolved items identified during this inspection are discussed in paragraph.
Review of Reportable Occurrences The inspector reviewed the Reportable Occurrence (RO) reports listed below to ascertain that NRC reporting requirements were being met and to determine the appropriateness of corrective action taken and planne Certain Licensee Event Reports (LER) were reviewed in greater detail to verify corrective action and determine compliance with the Technical Specifications and other regulatory requirements. The review included examination of log books, internal correspondence and records, review of SNSOC meeting minutes, and discussions with various staff member Within the areas inspected, no items of noncompliance or deviations were identifie LER 280/78-34, concerned certain spare process piping containment penetrations which had not been capped on the Auxiliary Building end as described in Section 5.2 of the FSA The licensee is taking action to cap these spare penetration While observing these penetrations, the inspector noted that several similar penetrations which were in use for systems such as RCS sample lines, did not appear to have double barriers as described in TS 5.2.B.1, although these in use penetrations are not described in the FSA The licensee and Stone and Webster are evaluating these in use penetrations to determine their adequacy. This I.ER remains open pending inspector review of this evaluatio '*
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-3-LER 280/78-37 concerned the late SNSOC review of a deviation to procedure OP-5. 1, "Filling and Venting the RCS".
The procedure deviation was subsequently reviewed and approve This item is close LER 280/78-38 addressed the quarterly calibration of the nuclear power range instrumentation which was not performed as required by TS 4. The calibration was subsequently performe The inspector noted that the system code designation was inappropriate on the LER form 366; the licensee has submitted a supplemental LER to correct this item. The LER is close LER 280/79-39 concerned the drift in pressurizer level channel I instrumentatio Appropriate corrective actions were take This item is close LER 280/78-41 concerned hydraulic snubber 1-WAPD-HSS-141B which was found inoperable due to low fluid level in the resevoi Initially, the licensee stated that the fluid had leaked out through faulty reservoir seals; however, upon further investiga-tion a slight crack was found in the reservoir glass and the seals were found intac A corrected LER has been submitte This item is close LER 280/78-43 concerned the dilution of boric acid storage tank (BAST) "A" due to an operator error in the valve alignmen Appropriate corrective action was taken following the occurrence and the personnel involved have been reinstructed as require This item is close LER 280/78-44 concerned the temporary loss of service water flow through the charging pump intermediate seal cooler due to the continuing valve stem corrosion proble Corrosion of the gate valve 1-SW-110 stem permitted the disc to fall and obstruct the
. service water flo The redundant system was operable. The licensee subsequently replaced the remaining non-stainless steel stems until the bronze ball valves can be installed. The inspector verified that the limiting conditions for operation were not exceede This LER is closed; however, followup on the Unit 1 and 2 valves continues. (See LER's 280/78-04 and 281/78-11). LER 280/78-45 addressed the failure of radiation monitor recorder 175 due to seizure of a bushing in the print mechanis While the trend recorder was inoperable, plant personnel observed the applicable radiation monitors and annunicators to detect trend Operability of the radiation monitors and alarms was not affecte This item is close *
-4-I.ER 280/78-46 concerned the failure of heat tracing circuit 25A on the boron injection tank recirculation line due to boric acid damag Low current was identified during routine surveillance testing. The heat tracing tape was replaced and verified operabl Since redundant circuits exist, the temperatures in the piping served by the affected circuits was maintained as required during the even However, due to similar failures, the licensee has initiated maintenance efforts to reduce boric acid leakage and engineering studies to consider the installation of more impervious heat tracin The licensee stated that these matters would be noted on subsequent LER' s of this nature. * The maintenance efforts initiated appear effective based on the recent reduced occurrence of heat tracing failures. This item is close LER 280/78-47 concerned the "C" steam generator primary to second-ary leakage which exceeded the allowable 0.3 gpm by approximately 0.02 gp When the tube leakage was verified to be above gpm, the reactor was shutdown as required by the Technical Speci-fications. The three steam generators were inspected and all leaking tubes were plugged prior to NRC approved startu The licensee has submitted a supplemental I.ER to correct the system code and cause subcode on I.ER Form 366. This item is close LER 280/78-48 concerned the dropping (insertion) of two control rod assemblies during startu The faulty circuit card in the control power cabinet was replaced. This item is close.
I.ER 280/78-49 addressed the identification of two inoperable snubbers during the conduct of the snubber inspection test during shutdow Leaking tube fittings reduced the fluid levels in the snubber reservoir The leaks were repaired and all Unit 1 snubbers were inspected and verified operable prior to startu Occasionally, fluid leaks can be expected to occur in hydraulic systems of this typ Periodic inspection of these snub be rs continues under TS 4.17. This LER is close LER 280/78-50 addressed the input error in the currently applicable LOCA-ECCS analysis for Surr The error was estimated to result in an increase of less than 20 Fin the peak clad temperatur This increase was assessed by the licensee and the margin to the TS and IOCFRS0.46 limits was found to be conservative enough to acconunodate the above non-conservatis A new analysis which includes more conservative methodology has been submitted to the NRC for approval. This LER is closed.
LER 280/79-01 identified a potential non-conservatism in the bot channel factor (Fq(z)) calculation due to the effects or presence of incore detector background. If the background is not properly
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subtracted out), a non-conservatism may exist. Data reviewed at Surry by the inspector and the licensee revealed no detector background readings above zero; however, the Fq program was revised to subtract detector background if present, and to alarm if the data is abnormal. This LER is close LER 281/78-36 concerned the missed surveillance on reactor coolant pump "C" bearing and motor temperature. The hourly surveillance was required because the fire protection system RCP heat detector was temperarily inoperable. This item is close IE Circular IE Circular 78-06, which addressed the potential common mode flooding of ECCS equipment rooms at BWR facilities, was received and reviewed by appropriate licensee personnel, and, adequate responsive actions are being take An engineering Study (78-29) is in progres This Circular is closed. The licensee stated that an engineering review of the reactor safeguards area sump pump equipment has been initiated due to the level of ground water found in the safeguards pit on November 13, 197 (See RII Report 50-280/78-33, paragraph 6.d.).
Review of Plant Maintenance and Periodic Testing Fire Protection System (FPS) - The inspector reviewed the following FPS Periodic Tests (PT) and certain FPS maintenance performed during 1978 to verify that the requirements of TS 3.21 and were met: PT 24. 5, Smoke Detectors PT 24.5A, RCP Heat Detectors - the licensee stated that this procedure would be revised to specify the Surry Unit tested (lor2). PT 24.6, Halon 1301 System - the nitrogen control cylinder pressure in a recent PT was below the manufacturers recom-mended pressure, however, a functional test was performed to demonstrate operability at the lower pressure; operability was verifie.
PT 24.4B and 24.4D, Fire Protection Systems PT 24.8, Fire Lockers PT 24.11, Fire Barriers - the licensee is revising this PT to specify the fire barriers to be inspected in each of the 33 area !. -
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- PT 24.4A and PT 24.11 will be identified as an open item (280/281/79-02-02) pending their revision as discussed above. Within the areas inspected, no items of noncompliance or deviation were identifie While inspecting fire barriers and electrical penetrations in the emergency switchgear and relay rooms, the inspector noted that certain potentially combustible materials such as plastic visqueen, tubing, and drawings had begun to accumulate in the Unit 2 relay roo The licensee took action to remove or properly file these material Where maintenance was performed on fire barriers or penetrations, the. inspector verified that protective foam or flamastic was reapplied as require Plant Operations The inspector toured the Unit 1 and Unit 2 control rooms and certain plant areas to observe that monitoring equipment and plant instrumen-tation was functioning as required, and that the facility operations were in accordance with the Technical Specifications. Plant logs and records were also reviewe Within the areas inspected, no items of noncompliance or deviations were identifie One unresolved item is identified in a. belo Specific areas of inspection are addressed belo While reviewing the licensee I s administrative controls over certain valves in the auxiliary building basement, the inspector noted that plant personnel may enter high radiation areas in the basement above, relying on *the Gai-tronics telephone paging system to provide the constant communication required. Technical Specification 6.4.B.1.f. states: Entrance to areas with radiation levels in excess of 1 R/hr shall require the use of the "buddy system" whereby a minimum of two indiviudals maintain continuous visual and/or verbal communication with each other; or other mechanical and/or electrical means to provide constant communica-tion with the individual in the area shall be provide Licensee management stated that the Gai-tronics telephone paging system provides the constant communication required. The inspector stated that this interpretation of TS 6.4.B.1.f is being discussed with NRC personnel. Unresolved Item:
Adequacy of the paging system to provide constant communication with personnel in hi'gh radiation areas is considered unresolved pending review by the inspector and his management (280/281/79-02-01).
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-7-The inspector observed the delivery of the two new lower steam generator units and the unloading of the first unit off the barge in preparation for the Unit 2 steam generator replacement outag No unloading problems occurre Although there was some speculation that the striking United Steelworkers Union at the Newport News Shipyards might attempt to picket the non-union Daniels Construction Company workforce at Surry, no picket lines were establishe Since the Surry Unit 2 steam generator replacement outage was delayed from January 26 to February 4, 1979, the inspector verified that the Conditions of the License, dated October 3, 1978, were not exceeded. Unit 2 was shutdown within six months of equivalent operation (RCS greater than 350°F) from August 1, 197 The inspector reviewed recent Unit 1 setpoint change requests for overtemperature delta T and high steamline flow; the parameters increased slightly due to the increased steam generator tube plugging in Unit 1.
The inspector reviewed the PT 28. 3, "Reactivity Anomalies",
results for 1978; no anomalies greater than 1% occurre The inspector reviewed purchase orders, receipt inspections, and certain conformance certificates associated with boric acid and sodium hydroxide received at the plant in 1977. The records of analysis on the boric acid crystals were in conformance with the purchase requirements; an independent chemical analysis on the sodium hydroxide was not available, although the supplier had certified that the solution was Rayon grade and contained less than 0.005 wt. per cent chloride. The licensee sampled the Unit 1 chemical addition tank; preliminary results indicate acceptable chemical compositio The inspector reviewed the Control Room Operator and Shift Super-visor Logs for January, 1979, verified that certain safety system valves and components in Units 1 and 2 were properly positioned and operable, and verified that the control rooms were manned in accordance with TS 6. The inspector reviewed certain alarmed annunciators in the control rooms, and noted that procedures have been approved for alarms H-2 on panel D of each uni Open item (280/281/78-35-0l) is close The inspector verified that the. licensee responded to the NRC request concerning containment purging during normal plant opera-
tion (November 28, 1978).
The response verified that the Surry atmospheric containments are not purged during operatio This item is close.
Plant Physical Protection The inspector verified the following by observation: Gates and doors in protected and vital area barriers were closed and locked when not attende Isolation zones described in the physical security plans were not compromised or obstructe Personnel were properly identified, searched, authorized, badged and escorted as necessary for plant access contro Security system alarms were properly documented and responded to; false security alarms were not a problem.