IR 05000293/1987051

Insp Rept 50-293/87-51 on 871102-06.No Violations Noted. Major Areas Inspected:Licensee Action on Previous Insp Findings,Power Ascension Test Program,& post-mod Training

ML20234B350
Person / Time
Site:	Pilgrim
Issue date:	12/16/1987
From:	Marilyn Evans, Lange D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20234B326	List: IR 05000293/1987051 ML20234B322
References
50-293-87-51, NUDOCS 8801050529
Download: ML20234B350 (5)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report N /87-51 Docket N License N DPR-35 Licensee: Boston Edison Company 800 Boylston Street Boston, Massachusetts 02199 Facility Name: Pilgrim Nuclear Power Station l

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Inspection At: Plymouth, Massachusetts l

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Inspection Conducted: November 2-6, 1987 l

Inspector: M( - b/uw I'd!/ 37 M. Evans, Operations Engineer, DRS d a te' /

Approved by: -

/ 2-/ 4 -7 7 D. Lange, ChiM , BWR- on, 08, DRS date Inspection Summary: Routine, Unannounced Inspection on November 2-6, 1987 (Report No. 50-293/87-51)

Areas Inspected: Routine unannounced inspection of licensee action on pre-vious inspection findings, Power Ascension Test Program, and post-modification trainin Results: No violations were identifie Note: For acronyms not defined, refer to NUREG-0544, " Handbook of Acronyms and Initialisms."

I 8801050529 871224 PDR

ADOCK 05000293 DCD

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m DETAILS 1.0 Persons Contacted Boston Edison Company

• R. Grazio, Field Engineering Section Manager

• P. Hamilton, Compliance Group Leader

• S. Hudson, Operations Section Manager D. Hughes, Requalification Training Program Supervisor i *E. Larsson, Quality Assurance, Surveillance Ledgett, Executive Assistant to Supervisor Nuclear

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i * *A. Morisi, Test' and Turnover Section

• K. Nicholas, Technical Section

• K. Roberts, Nuclear Operations Manager

• L. Schmeling, Restart Engineer

'*J. Seery, Technical Section Manager l G. Sherman, Requalification Training Program, Lead Instruction l

'- *E. Ziemianski, Nuclear Training Section Manager Other NRC Personnel l

• T. Kim, Resid2nt Inspector

• J. Lyash, Resident Inspector

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• Denotes those present at the exit meeting on November 6, 1987.

The inspector also contacted other members of the licensee's operations, technical and training staf .0 Licensee Action Concerning Previous Inspection Findings (0 pen) Unresolved Item (50-293/86-21-04) Licensee to evaluate testing methodology utilized to meet the intent of simulated automatic actuation (SAA) testing required by Technical Specifications (TS).

The inspector held discussions with a licensee representative regarding SAA. -The representative stated that the licensee will perform cold quick starts of both the High Pressure Coolant Injection System (HPCI) and Reactor Core Isolation Cooling System (RCIC) to satisfy the SAA Technical Specification (TS) requirements. Additionally, the licensee will analyze the need to perform this-type of testing for other systems with SAA TS requirement The inspector was satisfied with the licensee's response regarding SA j However, this item will remain open pending conduct of the HPCI and RCIC  !

testing and further review by the inspecto '

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(0 pen) Inspector Follow Item (50-293/87-25-01) As a result of the large number of significant plant modifications and procedure changes, an inspection of training given to licensed operators on major modifications and procedure changes affecting plant operations will be performed prior

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to restar The inspector reviewed training modules for several plant modifications and interviewed a significant percentage of the licensed operators regarding these modifications to determine the effectiveness of the trainin Based upon this review, the inspector identified two concerns which are further discussed in paragraph 4.2 of this report. This item will remain open pending further review of licensee training regarding modifications and procedure change .0 Power Ascension Test Program The licensee submitted a description of the PNPS Power Ascension Program to the USNRC for information and review per BECo Letter No.87-163 on October 15, 1987. The inspector discussed the program with several-licensee representatives.during this inspection. The inspector noted, based on the discussions, that the licensee is in the process of formally establishing this program. Therefore, a future inspection will be conducted to assess the licensee power ascension program when finalized, to assure compliance with regulatory requirements and licensee l commitment I 4.0 Post-Modification Training 4.1 Scope Licensed operator training regarding RFO-7 plant modifications was reviewed to determine the effectiveness of the training. (See paragraph 2.0, IFI 50-293/87-25-01.)

4.2 Discussion The inspector reviewed the training modules for the plant modifica-tions listed in Attachment A. The inspector interviewed a significant percentage of licensed operators regarding the training they had received. Based upon these interviews, the inspector identified two areas of concern. First, training conducted prior to completing the field installation for the Fire water Tie-in to RHR modification was ineffective. The inspector noted a misunderstanding  ;

regarding the planned final location of the removable spool piec '

In the lesson plan for this modification, the licensee stated that the normally removed spool piece would be stored in a normally locked cabinet and the watch engineer would have the key. However, none of the operators interviewed by the inspector were aware of this planned location. Second, the on-watch training presented to operators in the control room was not effective for all operators. This was evidenced by the lack of knowledge for some of the operators regarding the ADS Logic Modificatio ;

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The inspector discussed these concerns with representatives of the licensee's training department. They acknowledged the inspector's concerns and stated that the training department was considering presenting to the operators a :eview of all modifications during the first day of formal requalificatior training following plant restar Additionally, during the exit inte view conducted on November 6, 1987,-a representative of the licensee's training department stated that due to additional changes in the Fire Water tie-in to RHR Modi-fication regarding the spool piece location, a Field Revision Notice was issued and additional training will be conducted. Also, for all modification training conducted on-watch, additional training will be presented in a formal classroom setting prior to restar .3 Findings No violations were identified. The inspector will continue to review the effectiveness of licensee training and the licensee's response to the inspector's concerns identified above in a future NRC inspectio .0 Independent Verification As discussed in paragraph 4,2, the inspector independently assessed the effectiveness of the licensee's training for plant modification Con-cerns identified were presented to. licensee management and will be further reviewed during a future NRC inspectio ~ Unresolved Items Unresolved' items are matters about which more information is required in order to determine whether they are acceptable, an item of noncompliance or a deviation. An unresolved item reviewed during this inspection is discussed in paragraph .0 Exit Interview A management meeting was held at the conclusion of the inspection on November 6, 1987, to discuss the inspection scope, findings and obser-vations as detailed in this report (see paragraph 1 for attendees). No written information was provided to the licensee at any time during this inspection. The licensee did not indicate that any proprietary informa-tion was contained within the scope of this inspectio J

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. ATTACHMENT A Plant Modifications PDC 84-70, Analog Trip System PDC 87-30, ATWS Recirculation Pump Trip

' PDC 86-102, Reactor Feed Pump Trip /ATWS PDC 86-52B, Fire Protection System /RHRS Cross Tie PDC 86-73, ADS Logic PDC 85-07, Reactor Water Level Instrumentation Modification PDC 86-75, Enriched Boron Modification to SLCS PDC 86-70, SBGTS PDC 85-59, HPCI Exhaust Vacuum Breaker

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