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Insp Rept 50-213/86-25 on 861021-24.No Violation Noted.Major Areas Inspected:Review of Licensee Responses & Subsequent Analysis & Mods of Masonry Walls in Response to IE Bulletin 80-11,masonry Wall Design & Review of Work Packages
	ML20207G581
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	11/19/1986
From:	Strosnider J, Varela A; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	;
Shared Package
ML20207G551	List: ML20207G545; ML20207G581;
References
	50-213-86-25, IEB-80-11, NUDOCS 8701070336
	Download: ML20207G581 (10)
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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report No. 50-213/86-25

Docket No. 50-213

License No. DPR-61 Priority -

Category C.

Licensee: Connecticut Yankee Atomic Power Company

P. O. Box 270

Hartford, Connecticut 06101

Facility Name: Haddam Neck

Inspection At: East Berlin and Haddam Neck Plant

Inspection Conducted: October 21-24, 1986

Inspectors: ///f/4

_ A. Varela, Lead Reactor Engineer

fr date

NRC Contract Personnel: M. E. Nitzel, EG&G, Idaho

V. B. Call, EG&G, Idaho

Approved by: 8 ////9/#4

/J/' R. Strosnider, Chief date

LMaterials and Processes Section, EB, DRS

Inspection Summary: Inspection on October 21-24, 1986, Inspection Report

No. 50-213/80-25.

Areas Inspected: Special announced inspection by a regional-based inspector

and two contractor personnel at the licensee's engineering office and the

Haddam Neck plant site. The inspection encompassed review of licensee re-

sponses and subsequent analysis and modifications of masonry walls in response

to IE Bulletin 80-11, Masonry Wall Design. The inspection included a walkdown

of existing walls affecting safety related equipment, a review of design

analyses and a review of work packages on wall modifications.

Results: No violations were identified.

G701070336 861229

PDR ADOCK 05000213

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DETAILS

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1.0 Persons Contacted

NortheastUkilitiesandConnecticutYankeePowerCompany

W. Briggs, Supervisor, Generation Civil Engineering

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T. Bransfield, Plant Engineer

C. Chunglo, Civil Engineer

J. Mawson, Project Engineer

D. 9. McCory, Supervisor, Procurement QA

, * E. D'. Perkins, Licensing Engineer

0 * R. Smart, Manager, Generation Civil Engineering

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c * R. Werner, Vice President, Generation Engineering

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, URS Blume Consultant

L. Malik, Project Engineer

U.S. Nuclear Regulatory Commission

b P. D. Swetland, Senior Resident Engineer

attendees at Exit Meeting.

2.0 Inspection Purpose And Scope

The purpose of this inspection was to review with cognizant and

responsible licensee representatives at the corporate office and the

plant the' completeness of their responses to NRC/IE Bulletin 80-11,

Masonry Wall Design. The scope of the inspection included a review of

engineering design and quality assurance documentation relating to

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inspection, testing, analysis and modifications satisfying requirements

and licensee commitments with respect to the bulletin. A walkdown

inspection of the plant verified repairs and/or modifications relating to

the bulletin.

3.0 Review Criteria

The latest revision of the bulletin was used to define expected actions

by the utility. In addition, Temporary Instruction (TI) 2515/37 was used

to further define inspection requirements. Applicable sections of the

Code of Federal Regulations (10 CFR 50) were used.

4.0 Review Of Licensee Responses

The inspection team reviewed bulletin responses available from NRC files

prior to the inspection. These responses included reports addressing the

reevaluation methodology, acceptance criteria, wall configurations and

functions, structural adequacy, proposed modification plans, and

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modification schedules. Table I lists those documents reviewed prior to

the inspection. Questions of compliance or items requiring further

discussion were noted as items to be addressed while at the corporate

office or plant site. Questions relating to licensee responses were

forwarded to the licensee in advance of this inspection as a preliminary

agenda for discussion.

The inspection team reviewed additional material provided by the licensee

during the inspection. This material consisted of procedures governing the

original walkdown of masonry walls, work instructions and work requests

pertinent to masonry wall modification activities, masonry wall survey

packages from original walkdowns, reevaluation calculations, structural

adequacy calculations for all modifications, and modification detail

drawings. The pertinent documents described above for IEB 80-11 are

listed in Tables 2 and 3.

4.1 Findings:

It was determined from the review of the docurnentation described

above that, in general, all aspects of the work done in response to

the subject bulletin were acceptable. However, two unresolved items

were identified during the reviews described above. Further details

regarding these items are given below.

IEB 80-11 required the inspection and reevaluation of safety related

masonry walls to assure structural adequacy. In order to assure

continued compliance with bulletin requirements, physical conditions

such as absence of mortar cracking and assumed boundary conditions

must be maintained. The licensee was asked to provide a surveillance

plan for routine inspection of masonry walls subject to bulletin action

to demonstrate continued compliance. No formal plan for routine

surveillance currently exists. However, the licensee did produce an

outline for a procedure that would govern periodic surveillance of

the subject walls. The licensee stated that surveillance intervals

had not been decided at this time and that work was still in progress

in drafting the procedure. The licensee was requested to provide a

copy of this procedure at the earliest available date for NRC review

and was requested to provide surveillance intervals and walls included.

This is unresolved item number (50-213/86-25-01).

Criterion V of Appendix B to 10 CFR 50 requires that " Activities

affecting quality shall be prescribed by documented instructions,

procedures......". Questions regarding the procedural control over

mortar joint repair work were asked of the licensee. No evidence of

procedural control over mortar joint repairs, other that those ac-

complished in conjunction with another wall modification, was

produced. The licensee was asked to provide documentation clarifying:

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a. What procedures governed repair of mortar joints when not accomplished as

part of another wall modification.

b. What procedures govern repair of mortar joints performed by NUSCO maintenance.

The licensee stated that a mortar joint repair procedure that would govern

any repair activities required by the continued periodic surveillance program

was being developed. It was stated that this procedure would incorporate

research into the latest materials available for use in this type of repair.

The licensee was requested to provide a copy of the subject procedure for

NRC review at the earliest possible date. This is unresolved item number

(50-213/86-25-02).

5.0 Licensee Response To Above Unresolved Items:

The licensee representatives acknowledged the unresolved items and agreed

to respond by submitting to the NRC a draft of the surveillance plan pro-

cedure by December 31, 1986. The licensee representatives also agreed to

submit a draft copy of the mortar joint repair procedure for NRC review.

This procedure would be submitted prior to the end of February 1987.

Formalization of both procedures would then be completed prior to the

beginning of the next refueling outage (approximately June 1987).

6.0 Verification Walkdown Inspection

A physical inspection of certain masonry walls subject to bulletin action

was conducted. The walls included in this sample were chosen by the in-

spection team. The purpose of this walkdown was to verify samples of

inspections and/or modifications required by the bulletin. The walls

listed in Table 4 were examined.

No violations were identified.

7.0 Definition Of Unresolved Items

Unresolved items are matters about which more information is required in

order to ascertain whether they are acceptable, violations, or deviations

talative to the bulletin requirements. Unresolved items identified

curing this inspection are discussed in paragraphs 4 and 5 above.

8.0 Review Of Licensee Administrative Controls And Assurance Of Quality

The following documents were reviewed by the NRC inspector to determine

the adequacy of administrative controls and quality assurance of licensee

activities relating to his responsibilities and delegated responsibility

in engineering surveys, block wall modifications, and contractor (C. N.

Flagg) block wall repairs at the Haddam Neck plant.

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1. Northeast Utilities (NU) QA Program Topical report, applicable

revisions during IEB 80-11 activities.

2. URS/Blume QA Manual:

Design review No. 4.10 revision 7

Internal audits No. 6.1 revision 7

3. NU Generation Construction QC procedures and reports, surveillance of

C. N. Flagg block wall modifications, dated February 23, 1981

QC-151 Control of Deficiencies and Corrective Action

QC-152 Reporting of Defects and Noncompliance

QC-071 Material Receiving and Control

QC-131 Material Storage and Handling

QC-181 Quality Assurance Audit Program

4. NU QA nonconformance report reviews of C. N. Flagg's block wall

modifications and turn-over of as-built drawings for close-out and

acceptability.

5. NU QA surveillance report A 80-099 on welder qualifications.

6. NU audits of URS/Blume:

QA-3518 of October 1979, Supplier Evaluation and reevaluation -

February 1981

Audit A01419 of June 1981, Blume Topical Report

Audit A02192 of April 1984, Design Activities

NU QA follow-up correspondence with Blume relating to A01419

audit responses and corrective actions by Blume.

7. URS/Blume internal QA audit of masonry wall surveys and review of

design activities for conformance to their procedures.

This review observed that audit findings of deficiencies and nonconfor-

mances were adequately dispositioned, the required corrective actions were

approved, formally accepted and closed out.

Findings:

No violations were identified.

9.0 Summary

Based on the information examined during this inspection and the results '

of the field walkdowns, IEB 80-11 has been adequately responded to by the

licensee. His involvement and control in assuring quality and resolution

of technical issues from a safety standpoint appear adequate. IEB 80-11

is closed.

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10.0 Exit Meeting

The NRC inspector conducted an exit meeting participated in by EG&G

contract personnel, with licensee representatives (denoted in paragraph

1). The NRC inspector summarized the inspection findings and the

licensee acknowledged these comments. No written material, other than

that described in paragraph 4 (preliminary agenda for discussion) was

, provided to licensee personnel.

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Table 1 - DOCUMENTATION REVIEWED PRIOR TO INSPECTION

DOCUMENT DESCRIPTION

W. G. Counsil (Nusco) letter to B. 4. Grier (USNRC) dated 7-7-80

forwarding licensee's 60 day respense to IEB 80-11.

W. G. Counsil letter to B. H. Grier dated 11-4-80 transmitting

licensee's 180 day response to IEB 30-11.

W. G. Counsil letter to B. H. Grier dated 3-3-81 providing

status of IEB 80-11 activities and requesting schedule

extension.

W. G. Counsil letter to B. H. Grier dated 6-26-81 forwarding

information regarding the status of bulletin modification

activities.

8210150699 R. A. Clark (NRC) letter to W. G. Counsil dated 9-28-82

requesting additional information regarding responses to

IEB 80-11.

B10624 W. G. Counsil letter to R. A. Clark dated 12-3-82 forwarding

additional information regarding IEB 80-11 activities.

G. Lear (NRC) memo to J. Zwolinski (NRC) forwarding results of

a review of licensee submittals of additional information.

J. Zwolinski letter to J. F. Opeka (Connecticut Yankee Atomic

Power Co.) suggesting a site visit and meeting to discuss IEB

80-11 activities.

Internal NRC memo by F. M. Akstulewicz summarizing the

activities and results of the site visit and meetings held with

the licensee on October 28-30, 1985.

A05084 J. F. Opeka letter to C. I. Grimes (NRC) dated 12-31-85 forward-

ing additional information regarding IEB 80-11 activities.

J. F. Opeka letter to C. I. Grimes dated 2-18-86 describing

actions taken to monitor and repair cracks found in masonry

walls at Haddam Neck.

812016 J. F. Opeka letter to C. I. Grimes dated 3-7-86 describing the

repair methods used on the masonry walls identified in the

2-18-86 letter.

F. M. Akstulewicz letter to J. F. Opeka dated 3-26-85

forwarding NRC safety evaluation and technical evaluation report

(prepared by Franklin Research Center).

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Table 2 - DOCUMENTATION REVIEWED DURING INSPECTION

DOCUMENT DESCRIPTION

URS/Blume field work procedure for conducting field walkdowns

of masonry walls.

NEO 5.11 NUSCO procedure, Design Change Notices for Design Documents,

Revision 1A.

NUSCO specification No. SP-GC-38-80/ Construction Services for

Structural Modifications to Support NRC IEB 80-11.

Block Wall Modification Contractor, C. N. Flagg Quality Control

Project Procedures.

NEO 5.19 NUSCO engineering procedure to control modifications to

structures requiring seismic qualification reviews.

NUSCO outline of procedures for periodic surveillance of

masonry and repair of cracks in mortar joints in masonry walls.

NE0 3.03 NUSCO procedure for preparation, review and disposition of plant

design change requests (PDCR's).

8040 First generation field walkdown data files for the following

walls:

CYDG1001

CYDG1002

CYDG1003

CYDG1004

CYPAB101 (A-F)

CYPAB103

CYSF1001

CYSB1003

CYTB1008

CYTB1010

CYTB2003

URS/Blume Quality Assurance Manual Revision 7 dated 10-1-79.

URS/Blume Correspondence Log / Connecticut Yankee Black Walls

Project No. 8040-01 through 03.

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Table 3 - Calculation Packages Reviewed

CALC. NO. WALL

8040-53-CM-15 CYSF1001 (modifications)

8040-53-CM-17 CYPAB101A-F (modifications)

8040-53-CM-30 CYSF2001 (modifications)

8040-53-CM-12 CYSB1002 (modifications)

8040-53-CM-26 CYTB1008(modifications)

8040-03 CYSB1002 (reevaluation prior to mod.)

8040-53-CM-31 CYSB1003 (modifications)

8040-53-CM-24 CYTB1010 (modifications)

8040 CYCG1001 (reevaluation prior to mod.)

CYDG1002 (reevaluation prior to mod.)

CYDG1003 (reevaluation prior to mod.)

8040-53-CM-13 CYDG1001 (modifications)

8040-53-CM-14 CYDG1002 (modifications)

8040-53-CM-18 CYDG1003 (modifications)

8040-53-CM-19 CYDG1004 (modifications)

8040-53-CM-21 CYTB2003 (modifications)

CYPAB101F CYPAB101F (reevaluation prior to mod.)

CYPAB101A- CYPAB101A (reevaluation prior to mod.)

CYPAB101B CYPAB101B (reevaluation prior to mod.)

CYPAB101C CYPAB101C (reevaluation prior to mod.)

CYDG1004 CYDG1004 (reevaluation prior to mod.)

CYPAB102 CYPAB102 (reevaluation prior to mod.)

CYPAB103 CYPAB103 (reevaluation prior to mod.)

CYPAB104 CYPAB104 (reevaluation prior to mod.)

CYPAB107 CYPAB107 (reevaluation prior to mod.)

CYPAB108 CYPAB108 (reevaluation prior to mod.)

CYCT1001 CYCT1001 (reevaluation prior to mod.)

8040-53-CM-1 CYPAB102 (modifications)

8040-53-CM-2 CYPAB103 (modifications)

8040-53-CM-3 CYPAB104 (modifications)

8040-53-CM-4 CYPAB107 (modifications)

8040-53-CM-5 CYPAB108 (modifications)

8040-53-CM-6 CYCT1001 (modifications)

NOTE: All of the walls listed above except CYCT1001 were included

in the field walkdown conducted by the NRC inspection team.

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Table-4 - MASONRY WALLS FIELD VERIFIED

WALL ELEVATION (FT) LOCATION

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CYPAB101A-F 21'-6" PAB (Primary Aux. Bldg.)

.CYPAB102 21'-6" PAB

CYPAB103 21'-6" 'PAB

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CYPAB104 21'-6" PAB

CYPAB105 21'-6" PAB

CYPAB106 21'-6" PAB

CYPAB107 21'-6" PAB

CYPAB108 21'-6" PAB

-CYSB1002 41'-6" SB (Service Bldg.)

CYSB1003 41'-6" SB

CYSB2002 59'-6" SB

CYSB2003 59'-6" SB

CYDG1001 21'-6" DG (Diesel Gen. Bldg.)

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CYDG1002 21'-6" DG

CYDG1003 21'-6" DG

.CYDG1004 21'-6" DG

, CYSF1001 21'-6" SF (Spent Fuel Bldg.)

CYSF1002 21'-6" SF

CYSF2001 35'-0" SF

CYTB1007 21'-6"- TB (Turbine Bldg.)

CYTB1008 21'-6" TB

CYTB1009 21'-6" TB

-CYTB1010 21'-6" TB

3 .CYTB2003 37'-6" TB

CYTB2004 37'-6" TB

CYTB2005 37'6" TB

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