IR 05000440/1985055

From kanterella
Jump to navigation Jump to search
Insp Repts 50-440/85-55 & 50-441/85-20 on 850805-09 & 12-16. No Violations or Deviations Noted.Major Areas Inspected: Previous Insp Findings & Evaluation of Licensee Action Re IE Bulletins & SER Confirmatory Items
ML20134P246
Person / Time
Site: Perry  
Issue date: 08/30/1985
From: Knop R, Scheibelhut C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20134P189 List:
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.1.3, TASK-1.B.1.2, TASK-1.C.2, TASK-1.C.4, TASK-1.C.5, TASK-1.C.6, TASK-2.E.4.2, TASK-2.K.1, TASK-2.K.3.13, TASK-2.K.3.15, TASK-2.K.3.17, TASK-TM 50-440-85-55, 50-441-85-20, IEB-79-26, NUDOCS 8509060214
Download: ML20134P246 (7)


Text

{{#Wiki_filter:- _ - _ _. - -_ .. - +. .- U. S. NUCLEAR REGULATORY COMMISSION

REGION III

Report No.

50-440/85055 (DRP); 50-441/85020 (DRP) Docket No.

50-440; 50-441 License No.

CPPR-148; CPPR-149 Licensee: Cleveland Electric Illuminating Company Post Office Box 5000 Cleveland, OH 44101 Facility Name: Perry Nuclear Power. Plant, Units 1 and 2 Inspection at: Perry Site, Perry, OH ' Inspection Conducted: August 5-9 and August 12-16, 1985 , -

Inspector: C. H. Scheibelhut F I Date [ R'F(,0 Q g Approved by: R. C. Knop, Chief [[30/78 , ' Reactor Projects, Section 1C Date Inspection Summary Inspection on August 5-9 and August 12-16, 1985 (Reports No. 50-440/85055 (DRP); 50-441/85020 (DRP)) Areas Inspected: Routine safety inspection by a Regional Inspector of licen-see actions on previous inspection findings, evaluation of licensee action with regard to IE Bulletins and confirmatory items called for in the Safety , Evaluation Report. The inspection involved a total of 72 inspector-hours - ' onsite by one NRC inspector and includes 0 inspector-hours during off-shifts.

Results: No violations or deviations were identified.

J 8509060214 850830 PDR ADOCK 05000440 G PDR,. . - - - . . . . . . . - - . . . -.

_ _ _ .._ _.-. _ , ! .

l . , Details i 1.

Persons Contacted Cleveland Electric Illuminating Company , M. D. Lyster, Manager, Perry Plant Operating Department (PPOD) ! F. R. Stead, Manager, Nuclear Engineering Department (NED) i J. J. Waldron, Manager, Perry Plant Technical Department (PPTD) V. K. Higaki, Unit Supervisor, Nuclear Quality Assurance Department (NQAD) B. D. Walrath, General Supervising Engineer, NQAD E. C. Willman, Senior Engineer, NED B. S. Ferrell, Licensing Engineer, NED W. R. Kanda, General Supervising Engineer, PPTD B. B. Liddell, Operations Engineer, PPTD P. Russ, Compliance Engineer, PPTD ! N. J. Lehman, Staff Analyst, FPTD i' 2.

Licensee Actions on Previously Identified Items (92701) l (Closed) Open Item (440/85002-07(DRP)): " Applicant response to two a.

TPI-18 exempted situations which do not provide equivalent con-trols."

During a review of Test Program Instruction (TPI)-18, Rev.

l 3, " Temporary Alterations", the inspector found that in two situa-tions the necessary controls to assure restoration of electrical circuits did not seem to be present.

The licensee was investigating

] the concern.

,

i The licensee responded by revising the TPI so that restoration of temporary alterations had the necessary controls. Also the use of the TPI was restricted to restoration of alterations implemented in . accordance with previous revisions of the TPI.

Any future temporary - alterations will be in accordance with Plant Administrative Procedure (PAP)-1402, Rev. 2, " Control of Lif ted Leads, Jumpers,

Temporary Electrical Devices and Mechanical Foreign Items."

The inspector reviewed TPI-18, Rev. 4 and found that all restora- . tions would have the necessary controls.

PAP-1402, Rev. 2, was also reviewed and found to_have the necessary controls for temporary alterations.

In addition, the inspector reviewed the active MFI/LLJED log in the control room and eight examples were chosen at random for a field check of lifted leads and jumpers. Five were in - panels and three in motor control center cubicles.

In all cases, ! the log, lifted leads, jumpers, and tags were in accordance with the } procedure. This item is closed.

_ ! b.

(Closed) Open Item (440/85010-02 (DRP)): " PAP-0204 Housekeeping l Requirement Deficiency".

In the Final Safety Analysis Report (FSAR), the licensee committed to using the requirements of ANSI

. Standard N45.2.3-1973, " Housekeeping During the. Construction Phase of Nuclear Power Plants" with the exception that three housekeeping-zones would be established in lieu of the five required by the ' - standard.

Plant Administrative Procedure (PAP)-0204, '

- - - - . - - - - - - - - - - - - - - - - - - - - - - -.

, .

. " Housekeeping / Cleanliness Control Program", implements the require-ments of N45.2.3.

The inspector reviewed the procedure and was concerned that the three zona system and the procedures were too vague to ensure implementation of requirements equivalent to those in the standard.

The licensee amended the FSAR to remove any exceptions to the standard and revised PAP-0204 to bring it into agreement with the standard.

The inspector confirmed the amendment to the FSAR and reviewed the revised PAP-0204.

The review showed that PAP-0204 is now in agree-ment with the requirements of N45.2.3 without exceptions. This item is closed.

No violations or deviations were identified.

3.

Safety Evaluation Report Follow up Inspection Items (92701) The Of fice of Nuclear Reactor Regulation (NRR) has requested that Region III inspectors confirm that the licensee has acceptably implemented certain Three Mile Island (TMI) action items and confirmatory issues as described in the Safety Evaluation Report (SER) for Perry, Unit 1 (NUREG 0881 with Supplements 1 through 6).

In Inspection Reports 50-440/85022, 50-441/85012, and 50-440/85033, these items were listed as Open Items and ' entered into the Region III tracking system for future inspection.

The items reported below are the results of the inspection of certain of the items.

(Closed) SER Open Items (440/85022-03 (DRP)): "TMI Item I.A.I.3; a.

Verify that shift manning has been established in accordance with SER 13.1.2.2 and 13.5.1.4".

The licensee has written three Plant Administrative Procedures (PAPS) to implement the FSAR commitments and SER evaluation of the commitments concerning shift manning and practices. They are: PAP-0104, Rev. 1, " Operations Section Organi-zation", PAP-0110, Rev. 1, "Shif t Staffing", and PAP-0201, Rev. 1, " Conduct of Operations".

The inspector's review of these procedures and TMI Item I. A.1.3 requirements show them to be in agreement.

This item is closed.

b.

(Closed) SER Open Item (440/85022-06 (DRP)): "TMI Item I.B.1.2; Determine that the applicant has established an independent safety engineering group (SER 13.4.3 and 13.5.1.6)".

TML Item I.B.1.2 required the establishment of an onsite independent safety engineer-ing group (ISEG) and gave guidelines for its composition and duties.

The licensee amended the FSAR to incorporate the require-ments. The SER noted that the required ISEG was chartered and indicated the details of the charter.

The SER also noted that implementing procedures would be developed to ensure that the requirements of the charter and the intents of NUREG-0737 were met.

J

. . The licensee has written the following implementing procedures: Nuclear Engineering Department Procedures (NEDP)-0201, " Independent Safety Engineering Group Operation" and Perry Operations Procedure (POP)-0203, " Independent Safety Engineering Group Operations".

The inspector reviewed the procedures, TMI Item I.B.I.2, FSAR Section 13.4.3, and SER Sections 13.4.3 and 13.5.1.6.

The review showed that the intents of TML Item I.B.I.2 contained in NUREG-0737 were met in their entirety.

This item is closed.

c.

(Closed) SER Open Item (440/85022-08 (DRP)): "TMI Item I.C.2; Determine that the licensee has established procedures for shift and relief turnover procedures in accordance with SER 13.5.1.7".

The licensee wrote Operations Administrative Procedure (OAP)-0103, "Shif t Relief and Turnover" to prescribe these actions.

The inspector's review of the OAP showed that it met the require-ments of TMI Item I.C.2.

This item is closed.

d.

(Closed) SER Open Item (440/85022-09 (DRP)): "TMI Item I.C.4; Determine that procedures have been implemented to limit access to the control room in accordance with SER 13.5.1.9".

In PAP-0201, Rev. 1, " Conduct of Operations", the licensee has included pro-visions that establish the authority and responsibility of the person in charge of the control room to limit access.

It also establishes the line of authority in case of an emergency and limits it to persons possessing a current senior reactor operator's license. Also defined are lines of communication and authority for plant management not in direct command of operation.

The inspector's review of the PAP showed that it implements the above features in accordance with TMI Item I.C.4 and SER 13.5.1.9.

This item is closed.

(Closed) SER Open Items (440/85022-10 (DRP)), "TMI Item I.C.5; e.

Determine that procedures have been established to provide operating experience to the staff (SER 13.5.1.10)."

The licensee wrote Plant Operating Procedure (P0P)-1503, Rev. O, " Operating Experience Re-view", Nuclear Engineering Department Procedure (NEDP)-1504, " Operating Experience Review", and Project Administration (PA)-1601, " Evaluation of IE and INPO Documents" to comply with Item I.C.S.

The inspector's review of the procedures showed that they implement the requirements of TMI Item I.C.5 in all respects. This item is closed.

f.

(Closed) SER Open Item (440/85022-11 (DRP)): "TMI Item I.C.6; Determine that controls have been establihed for verification of correct performance of operating activities (SER 13.5.1.11 and SSER2 13.5.1.11)".

In supplement 2 to the SER, the staff found that the commitments to write procedures responsive to the requirements of THI Item I.C.6 were acceptable.

This open item is to verify that the procedures have been written and issued.

J

. .* The following procedures are pertinent te the implementation of the requirements of IMI Item I.C.6: 1.

Equipment Control Procedures PAP-1401, " Equipment Tagging" PAP-1402, " Control of Lif ted Leads, Jumpers, Temporary Electrical Devices and Mechanical Foreign Items" PAP-0205, " Operability of Plant Systems" 2.

ALARA Procedures PAP-0118, " Operational ALARA Program" 3.

Surveillance Activities PAP-1105, " Surveillance Test Control" TAP-0503, " Preparation of Technical Specification Surveillance Instructions" 0AP-1701, " Tracking of LCOs" These procedures fit into the areas of concern in TMI Item I.C.6 as follows: 1.

Surveillance Testing TAP-0503 and PAP-1105 2.

System Release for Maintenance or Surveillance Testing PAP-0205, PAP-1402, and PAP-0118 - 3.

Requirements for Independent Verification PAP-0205 and PAP-1401 4.

Equipment Status PAP-0205 and 0AP-1701 5.

System Return to Service PAP-0205 With the issuance of these procedures that comply with the require-ments of TMI Item I.C.6, this item is closed.

g.

(Closed) Open Item (440/85022-20 (DRP)): "THI Item II.E.4. 2; De ter-mine that containment isolation is complete (SER 3.9.3.2.1 and 6.2.7 and SSER2 6.2.7)".

The SER for the FSAR raised a number of que.stions (Confirmatory Issue (23)) regarding compliance with TMI Item II.E.4.2 that deals with containment isolation. The licensee provided additional'information which the staff reviewed.

In sup-plement 2 to the SER, the staff considered the response acceptable

5 ) ]

.. ano stated that Confirmatory Issue (23) was resolved.

One of the questions was the specification of the minimum containment pressure setpoint which would be provided and reviewed as part of the Technical Specifications for Perry.

The " proof and review" copy of the Perry Technical Specifications lists this setpoint as _<1.68 psig.

Since this final piace of in-formation has been supplied for review by the staff, this item is closed.

h.

(Closed) SER Open Item (440/85022-27 (DRP)): "TMI Item II.K.1.10; Verify that controls have been instituted to ensure that critical valves operability staLus is known in accordance with SER 13.5.2.4.

Also see IEBs 79-05, 79-06, and 79-08".

Plant procedures PAP-0205, " Operability of Plant Systems", and PAP-1401, " Equipment Tagging", address the concerns of Item II.K.1.10.

The inspector reviewed the procedures and found that the concerns of the item have been addressed and ensure that the operability status of safety-related systems is known to plant operators. This item is closed.

i.

(Closed) SER Open Item (440/85022-31 (DRP)): "TMI Item II.K.3.17; Determine that controls are in place to report emergency core cool-ing system (ECCS) outages (SER 6.3.3)".

The licensee committed to reporting outages of ECCS on an annual basis to meet the require-ments of Item II.K.3.17.

PAP-1604, " Reports Management", details the administrative controls for the preparation, review, approval and tracking of reports submitted to outside agencies.

The inspector's review of the procedure showed that it requires an annual report of ECCS outages to be submitted to the NRC on March 1 of each year.

Since the necessary controls are in place, this item is closed.

J.

(Closed) SER Open Item (440/85022-42 (DRP)): " Confirmatory Issue 27 (SER 1.10); Determine that the scram discharge volume level monitor-ing system has been installed and tested (SSER4.7.2.2.4)".

In an inspeccion conducted by Licensing Branch No. 1, Division of Licens-ing, the installation of the scram discharge volume (SDV) level monitoring system was confirmed.

This inspection was documented in a letter from B. J. Youngblood to M. R. Edelman dated May 31, 1985.

While reviewing licensee actions taken to resolve a 10 CFR 50.55(e) report, the inspector confirmed that the SDV level monitoring system had been tested.

This is documented in Inspection Report 50-440/85047 (DRP); 50-441/85019 (DRP).

This item is closed.

k.

(Closed) SER Open Item (440/85033-10 (DRP)): "TMI Item II.K.3.13; Verify that the applicant has modified the reactor core isolation cooling system (RCIC) to provide automatic restart on a low reactor water level signal (SER 5.4.1)".

The licensee made the necessary changes to permit automatic restart of the RCIC systcm on a low reactor water level signal.

This feature was successfully tested

)

h.5 +_ .-. o.MA

4 4-- u

.,-*,.h-J L

. ? during Preoperational Test Procedure IE51-P-001, " Reactor Core Isolation Cooling".

This item is closed.

1.

(Closed) SER Open Item (440/85033-11 (DRP)): "TMI Item II K 3 15; ... Verify that a time delay relay has been installed in the RCIC system ' isolation logic from the pressure instruments used to sense exces-sively high steam flow / steam supply line break (SER 5.4.1)".

The licensee made the necessary changes to inccrporate a time delay relay as indicated above.

This feature was successfully tested during Preoperational Test Procedure IE51-P-001, " Reactor Core ! ' Isolation Cooling".

This item is closed.

No violations or deviations were identified.

4.

Evaluation of Licensee Action with Regard to IE Information Bulletins (92717)

For the IE Laformation Bulletin listed below, the inspector verified that the Bulletin was received by the licensee management, that a review for applicability was performed, and if the Bulletin was applicable to the facility, appropriate corrective actions were taken.

. t (Closed) IE Bulletin No. 79-26 (440/79026-BB, 441/79026-BB): Boron Loss " r from BWR Control Rods".

The General Electric Company (GE) informed the ' NRC that under certain conditions of high burnup in control rods, the ' rods could crack and the coolant then slowly leach out boron-containing ! material.

This would lead to a loss in the effectiveness of-the control rods.

GE also issued a Service Information Letter (SIL) No. 157 on the sub-ject.

The letter discussed the problem and recommended five actions to improve their customer's control rod management program.

In essence, it 10 from 42% to 34%. reduces the maximum depletion of B ' The licensee wrote Fuel and Technical Instruction (FTI)-A03 to incorpor-ate the SIL recommendations.

The inspector reviewed the ETI and concludes that recommendations have been incorporated into the licensee's control rod management program.

This item is closed.

. . No violations or deviations were identifed.

5.

Exit Interview (30703) The inspector met with the resident inspector and licensee representa-tives (denoted in paragraph ~1) at the conclusion of the inspection on August 16, 1985.

The resident inspector summarized the. scope and find- ' ings of the inspection.

The licensee-acknowledged the inspector's find-ings. The licensee.did not indicate that any of the information disclosed during the inspection could be considered proprietary in nature.

,

'

- - - - -. - . - - }}