IR 05000029/1989005

Insp Rept 50-029/89-05 on 890403-07.No Violations Noted. Major Areas Inspected:Review of Util Actions on NRC Identified Previous Concern Re Generic Ltr 83-28,Item 2.2.2, Vendor Interface & commercial-grade Item Program

ML20246L024
Person / Time
Site:	Yankee Rowe
Issue date:	05/02/1989
From:	Blumberg N, Dev M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20246L021	List: IR 05000029/1989005 ML20246L015
References
TASK-07-03, TASK-2.E.1.2, TASK-7-3, TASK-RR, TASK-TM 50-029-89-05, 50-29-89-5, GL-83-28, NUDOCS 8905180219
Download: ML20246L024 (6)

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U.S. NUCLEAR REGULATORYCOMMISSION-

REGION I

Report N /89-05 L Docket N License N DPR-3 Licensee: Yankee Atomic Electric Company 580 Main Street Bolton, Massachusetts 01740-1398 Facility Name: Yankee Nuclear Power Station Inspection At: Rowe, Massachusetts Duration: April 3 - 7,1989 Inspector: f / b b i

M.Dev,ReptorEngineer / Date Approved By:

N. Blumberg, Chipf / Date Operational Probrams Section, 09', DRS Inspection Summary: Routine unannounced inspection conducted on April 3-7, 1989 (Inspection Report No. 50-029/89-05)

Areas Inspected: Review of the licensee's action on NRC identified previous concern pertaining to Generic Letter 83-28, Item 2.2.2, Vendor Interface, licensee's Commercial Grade Item program implemen' , ion, and compliance to 10 CFR 50 62, ATWS Rul i Inspection Results: The licensee's action to update vendor manuals has been protracted. Management has not been very aggressive in resolving NRC concerns pertaining to this issue. The station Commercial Grade Item procurement program

' implementation is adequate. Based on the evaluation of the licensee's response, th> Commission has granted an exemption to 10 CFR 50.62, ATWS Rul No violations were identifie L_._m____._ _ _ _ _ _ _ . _ _ . . _ . _

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-DETAILS OF INSPECTION 1.0 Persons Contacted Yankee Atomic Electric Company (YAEC)

L. Bozek,.QA Supervisor

• R. Dobosz, Stockroom Supervisor S. Fournier, Lead System Engineer

• M. Gilmore, Technical Services Engineer J. Haseltine, Project Director

• T. Henderson, Assistant Plant Superintendent B. Jwaszewski, Staff Engineer

• J. Kay, Technical Services Manager *

'*D. King, Maintenance Support Supervisor

• Kowalski, Senior Plant Engineer

• Mellor,. Technical Director

• Mitchell, Maintenance Manager

• Neumann, QA Engineer

• Wood, Administrative Manager (*) Denotes those who attended the exit meeting on April 7, 1989.

The inspector also contacted licensee's other technical and administrative personnel during the course of this inspectio Note: Documents reviewed for this inspection are listed in /.ttachment (1).

2.0 Licensee's Action on the NRC Identified Previous Concern (IP 92701)

(0 pen) Unresolved Item (50-029/85-12-02): This item pertains to the '

licensee failure to establish a program for assuring that vendor furnished information for safety-related equipment is complete, current and correc Generic Letter (GL) 83-28 required the licensee to update plant procedures and instructions to reflect vendor supplied current information. In absence of such information, sufficient attention was warranted to maintain, repair or replace the equipment to assure its reliability commensurate with its safety functio In subsequent Systematic Analysis of the Licensee Performance (SALPs) evaluations (1985 through 1988) the NRC identified that the licensee's programmatic procedure did not provide for the accuracy and control of the licensee's vendor manuals in us These concerns were also reiterated in the NRC Inspection Report 50-029/88-2 In one instance, the report indicated that the recurring failure of West-inghouse Type SC-1 relays associated with Main Coolant Flow Trip was attributed to the unsuitability of these relays for this particular appli-cation. Although, the vendor (Westinghouse) had issued service

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information (Service Bulletin I.L.4-766.1, July 1978) for these relays, the information was neither available nor reviewed by the plant personnel to verify its applicab.111ty at YNPS. In another instance, discrepancies in design data of Rochwell Non-Return Valve Vendor Manual RAL-5186 indicated that the manual was not adequately reviewed for its technical adequacy prior-to use. These concerns have previously been resolved and the corrective actions had been implemente The inspector noted that the licensee has established procedure YR-WI-21, Identification, Evaluation and Control of Vendor Manuals for the Plant Life Extension Program. The procedure has divided the licensee vendor technical manuals (VTMs) update program into five phases: (1) Identification and Assignment fer Evaluation, (2) Walkdown and Evaluation, (3) Plant Procedures Verification, (4) Manufacturer Revision Verification, and (5) VTM Control and Distribution. The licensee has completed the first phase of the program, and the procedure for control and distribution of the vendor technical manuals (phase 5) of the program is currently under station review. The other phases are not yet coh 71eted. The completion of this program will take about 2-1/2 years, and eventually will update the vendor manuals for the station safety-related eqiipment. The inspector discussed with the licensee's representatives the basic concerns addressed in the NRC inspec-tion finding (Inspection Repor. 50-029/85-12-02). In order to resolve these concerns the licensee nem s to: (1) establish a list of updated vendor technical manuals, (2) re/iew the applicability of these manuals to the station equipment, and (3) verify that the station maintenance, surveillance and operating procedures had adequately incorporated and referenced associated vendor technical information furnished in these manuals. The licensee has not completed the update of the Vendor Manual Program. A licensee representative stated that these concerns will be resolved and the corrective actions implemented by October 198 Based on the above review and discussion with the licensee representatives, the inspector determined that the licensee's action to resolve the NRC concern has been protracted. This item remains ope .0 Licensee's Commercial Grade Items Procurement Program (IP 38703)

3.1 Scope The scope of this inspection was to verify the adequacy of the licensee's commercial grade procurement program for items intended for safety grade application .2 Program Review and Findings I

l The licensee Project Procedure 22 provides for the evaluation and dedication of commercial grade items for safety class application at Yankee Nuclear Power Station (YNPS). Accordingly, a responsible

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engineer evaluates the items, determines its critical characteristics to be verified, and identifies methods of acceptance, such as, use of special test and inspection, commercial grade survey of the suppliers, or source verification. This procedure is employed in conjunction with Administrative Procedure AP-0211, Material and Service Procure-ment Program, and Project Precedure PP-08, Material and/or Service Purchase Requests (MPRs). The inspector noted that the licensee QA department has established procedure 0QA-XVIII-9, Commercial Survey and has conducted vendor surveillance of two vendors supplying commercial grade items. The results of the vendor surveillance were acceptabl The inspector interviewed several individuals, including engineers, and procurement and stores personnel associated with the procurement of station commercial grade items. These individuals were properly trained and indoctrinated in the licensee's commercial grade item procurement program. The inspector also reviewed selected procurement documentation to determine the adequacy of the licensee program implementation, and walked through the station warehouse to verify storage and handling of commercial grade items. The following items were verified for their stock code, vendor part identification number, quantity and location in the warehouse, and adequacy of receiving inspectio Purchase Orders Part N Items QA 40610 171U118882 & Nuclear Instrumentation Cable 171U118892 Connectors QA 40642 47I2156769 Barksdale Pressure Switch QA 40747 ---

Overload Heaters QA 40825 RKN-76UU & Jamesbury Ball Valves Service RKQ-15 Kits 3.3 Conclusions Based on the review of the licensee procurement of commercial grade l items, its dedication for safety-related applications, and interviews '

with the personnel associated with the program, the inspector determined that the licensee's commercial grade item procurement program implementation is adequate. No deficiencies were identifie The inspector did not have any further questions at this tim .0 Licensee Compliance to 10 CFR 50.62, ATWS Rule (IP 25020)

The Code of Federal Regulations, in 10 CFR 50.62, " Requirements for reduction of risk from anticipated transients without scram (ATWS) events for light-water-cooled nuclear power plants" requires, that each pressurized water reactor must have equipment from sensors to final actuation device, that is diverse from the reactor trip system, to automatically initiate the emergency feedwater system and initiate turbine trip under condition indicative of an ATWS.

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W By letters dated Octobe'r 25, 1985, January 22, 1988, and April 25. 1988,'

the licensee requested an exemption from the requirements of 10 CFR 50.6 The licensee cited the Probabilistic Safety Study which indicated that ATWS induced core melt accident frequency was not a major risk contributor-6 (about 1x10 per year) at YNPS. Previous studies of the YNPS emergency feedwater system conducted for NUREG-0737 Item II.E.1.2, and SEP Topic VII-3 concluded that automatic initiation of emergency feedwater was unnecessary. The main feedwater system is unique, in that it consists of ten pumping trains and eight flow paths to supply feedwater to the steam generators. A steam driven emergency feedwater pump and a new safe shut-down system assure availability of feedwater. The licensee also stated  ;

that the reactor trip breakers have not experienced any failure to open either in testing or on actual demand for over 25 years of operatio The population density around the plant is very low (60 people within 1-mile radius and 1600 within 5-mile radius) and has remained stable since the plant was built. In letter dated April 25, 1988 the licensee committed to operate the plant within the conditions assumed in the safety studies and maintain the moderator temperature coefficient at hot, full power, with equilibrium Xenon, no less negative than -5x10-5 delta k/k F for every fuel cycl Based on the evaluation of the licensee's response to 10CFR 50.62, the staff had previously determined that the application of the regulation was not necessary to achieve the underlying purpose of the rule. The NRC granted the licensee an exemption from the requirements of 10CFR 50.6 The inspector reviewed the licensee documentation and discussed with the cognizant personnel the conditions of special circumstances mentioned above, and the licensee's action to reduce the risk and mitigate the consequences of an ATWS event. The inspector did not have any further questions at this tim .0 Management Meetings (IP 30703)

The licensee management was informed of the scope and purpose of the inspection at the er. trance interview on April 3,1989. The findings of the inspection were discussed with the licensee representatives during the course of this inspection and presented to the licensee management at the conclusion of the inspection on April 7,1989 (see Paragraph 1.0 for attendees).

At no time during this inspection were written materials provided to the licensee. The licensee did not indicate that any proprietary information was involved within the scope of this inspectio _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - - _ _ _ _ _

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Attachment -1 Documents Reviewed

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1.0 Procedures AP-0075, Vendor Equipment Technical Information Program, Rev 2, 8/87 AP-0211, Material & Service Procurement Program, Rev 16, 11/88 YR-WI-21, Work Instruction.for Identification, Evaluation and Control of Vendor Technical Manuals, Rev 0, 11/88 Project Procedure 08, Material and/or Service Purchase Request, Rev 0, 7/88 Project Procedure 22, Dedication of Commercial Grade Items for Safety Class Applications, Rev 0, 7/88

.0QA-XVIII-9, Commercial Survey, Rev 0, 2/89

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2.0 Miscellaneous Licensee's Letter FYR 85-107, Exemption from ATWS Rule, October 15, 1985 Licensee's Letter FYR 88-17, Exemption from ATWS Rule, January 22, 1988

, Licensee's Letter FYR 88-55, Exemption from ATWS Rule, April 25, 1988 US NRC Letter Dated May 26, 1988, Issuance of Exemption to 10 CFR 50.62, ATWS - Yankee Nuclear Power Station i