IR 05000387/1981024

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IE Insp Repts 50-387/81-24 & 50-388/81-12 on 811019-23.No Noncompliance Noted.Major Areas Inspected:Administrative Controls for safety-related Activities
ML17139A488
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 11/05/1981
From: Blumberg N, Caphton P
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML17139A487 List:
References
50-387-81-24, 50-388-81-12, NUDOCS 8112090160
Download: ML17139A488 (12)


Text

U;S.

NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Report No.

Docket No.

License No.

Licensee:

50-387/81-24 50-388/81-12 50-388 CPPR-101, CPPR-102 Region I Prior ity Penns lvania Power and Li ht Com any 2 North Street Allentown, Pennsylvania 18101 Category A

Facil ity Name:

Inspection at:

Susquehanna Steam Electric Station, Units 1 and

Berwick, Pennsylvania Inspection conducted:

Inspectors:

tober 19-23, 1981

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eac or nspec or Cate signed date signed Approved by:

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. Caphton, Chief, Management Programs Section, Engineering Inspection Branch date signed z~~ El d te signed Ins ection Summar

Ins ection on October 19-23, 1981 Combined Ins ection Re ort No. 50-387 81-24 and 50-388/81-12 A~:

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f administrative controls for safety related activities and station tour.

The insoection involved 32 inspector-hours onsite by one region-based inspector.

Results:

Noncompliances

- None.

Region I Form 12 (Re

~n~n 7n 8ii2090160 Biiiii7 PDR ADOCK 05000387

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DETAILS 1.

Persons Contacted J. Blakeslee G. Butler R.

Byram

'F. Eisenhuth F. Graber

'J.

Graham J.

Green G.

Hanson

'H. Keiser

"L. O'Neil

"R. Prego D. Sitler R. Stotler J.

Wharton Mechanical Maintenance Supervisor Instrument

& Control (I&C)/Computer Maintenance Supervisor Supervisor of Maintenance Senior Compliance Engineer Operations Consultant (Quadrex)

Staff Assistant Quality Assurance (QA) Supervisor Operations Engineering Consultant (Quadrex)

Superintendent Susquehanna Steam Electric Station (SSES)

Technical Supervisor Senior Project Engineer-NQA Operations Senior Results Engineer Operations Supervisor of Security Supervisor Nuclear Records System USNRC

  • J.

McCann

  • G. Rhoads Resident Inspector Resident Inspector
  • Denotes those present at the exit interview.

2.

Station Administrative Controls a.

Administrative controls governing safety related activities were in-spected to determine their conformance with the requirements of 10 CFR 50, Appendix B, "Quality Assurance Criteria for Nuclear Power Plants

..."; Technical Specification, Section 6, "Administrative Controls";

Regulatory Guide 1.33-1978,

"Quality Assurance Program Requirements (Operation)";

ANSI N18.7-1976,

"Administrative Control and Quality Assurance for... Nuclear Power Plants";

and other applicable Regula-tory Guides and ANSI Standards as specified in the FSAR, Section 17.2,

"Quality Assurance During the Operations Phase."

This inspection was conducted during the preoperational phase of construction for Susquehanna Unit

and the construction phase for Unit 2; however, the procedures reviewed will be required for both Units 1 and 2 subsequent to an operating license (OL) for each unit.

The inspector also discussed with various licensee representatives their expected program for conduct of safety related activities upon receipt of OL.

The following procedures were reviewed:

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AD-QA-100, Station Organization and Responsibilities, Revision 0, August 10, 1981; AD-QA-101, Procedure Program, Revision 0, August 10, 1981; AD-QA-103, Protecti ve Permi t and Tag System, Revi si on 0, September 7,

1981; AD-00-003, PORC Procedure, Revision 1, February 20, 1980; AD-QA-110, Station Fire Protection Program, Revision 0, October 8, 1981; AD-QA-306, System Status and Equipment Control, Revision 0, October 12, 1981; AD-TY-422, Interim Surveillance Testing Program, Revision 0, October 12, 1981; AD-QA-502, Work Authorization System, Revision 0, October 12, 1981; AD-TY-602, IKC Surveillance Draft Procedure Verification Program, Revision 0, August 10, 1981; AD-00-004, Receiving and Distribution of Station Documents, Revision 0, October 26, 1979; AD-00-025, Conduct of Maintenance, Revision 0, May 27, 1980; AD-00-026, Conduct of Operations, Revision 0, November 13, 1979; AD-00-040, Control and Calibration of Plant Measuring and Test Equipment (METE), Revision 1, July 24, 1980; AD-00-041, Control of Plant Instrumentation, Calibration, Preventive and Corrective Maintenance, Revision 1, July 14, 1980; AD-00-048, Housekeeping and Cleanliness Control, Revision 0, March 26, 1979; AD-00-089, Computerized Preventive Maintenance System, Revision 0, August 29, 1980; and, AD-00-042, Control of Temporary Modifications, Revision 0, July 24, 198 b.

~Findin s

The inspection was conducted to determine the station's readiness to adhere to regulatory requirements upon issuance of an operating license (OL).

Since an OL has not been issued, deficiencies identified during this inspection are identified as open items (inspector follow items)

rather than items of noncompliance or unresolved items.

The term

"Licensee",

as used in this report, refers to the holder of the con-struction permits for Units

and 2.

The following items were identified for corrective action or further licensee review.

Licensee actions concerning these items will be reviewed by NRC:RI during future inspections:

(1)

Procedure AD-gA-101 states that newly approved procedures or procedure revisions are effective on the date of issue by the Document Control Center (DCC).

The inspector informed the licensee that the time frame for issuance of procedures must be established procedurally in order to assure the controlled timely issuance of procedures and revisions after their approval.

A licensee representative stated that better control of procedure issue dates would be established (387/81-24-01).

(2)

Procedure AD-gA-101 authorizes PORC review of procedures by use of a routing slip to PORC members.

A meeting is not required if there are no adverse comments.

The inspector informed the licensee of previous NRC interpretations concerning this type of PORC review which states that formal PORC review must take place at a

PORC meeting, which has a quorum of PORC members present, so that free and open discussion can take place.

However, a pre-meeting routing of PORC review items is acceptable.

~ The licensee concurred with the inspector and stated that the procedure would be revised to assure that final PORC review occurs at a formal PORC meeting.

In addition, the licensee informed the inspector that, to date, all final PORC reviews for currently approved procedures had taken place during a

PORC meeting (387/81-24-02).

(3)

Procedure AD-00-003,

"PORC Procedure",

does not adequately reflect the requirements of Section 6 of the current proposed Technical Specifications for Unit l.

A licensee representative stated that this procedure was under review and would be revised to reflect the latest Technical Specification requirements (387/81-24-03).

(4)

Procedure AD-gA-502 states which documentation would be main-tained as part of records for a completed work package.

This list was not inclusive and documents such as cleanliness and weld records had been omitted.

A licensee representative stated that this procedure would be further reviewed regarding the makeup of contents of the final maintenance package.

(387/81-24-04)

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(5)

Several administrative procedures which were approved and issued during 1979 and 1980 are out of date in that they reference incorrect or nonexistent procedures, do not contain referenced forms as part of the procedure, or are inconsistent with more recently issued administrative procedures.

Some examples are procedures:

AD-00-004, "Receiving and Distribution of Station Documents";

AD-00-040, "Control and Calibration of Plant Measuring and Test Equipment";

AD-00-041, Control of Plant Instrumentation, Calibration, Preventive and Corrective Maintenance";

AD-00-025, "Conduct of Maintenance";

and, AD-00-026,

"Conduct of Operations."

A licensee representative stated that this problem had been recognized and that the above procedures and others would be revised by January 1,

1982 (387/81-24-05).

(6)

Procedure AD-00-026 appeared not to contain all of the guidelines specified in IE Circular 81-02,

"Performance of NRC-Licensed Individuals While on Duty".

A licensee representative stated that AD-00-026 was currently being revised to contain the commitments to Three Mile Island Lessons Learned and would also be reviewed for conformance to IE Circular 81-02 (387/81-24-06).

(7)

Cleanliness Zones specified in Procedure AD-00-048 did not appear to completely conform to those specified in ANSI N45.2.3,

"Housekeeping... [for]... Nuclear Power Plants".

A licensee representative stated that he felt that AD-00-048 currently reflected the requirements of ANSI N45.2.3.

However, since the procedure was currently under revision for other reasons, he stated that AD-00-048 would be reviewed to assure that all applicable requirements of ANSI N45.2.3 were considered by the procedure (387/81-24-07).

(8)

The inspector observed that no procedure appeared to address system cleaning.

A licensee representative stated that a

new procedure, AD-gA-S03, was in preparation to cover this area (387/81-24-08).

(9)

The inspector reviewed the procedure index against the procedures index listed in Regulatory Guide 1.33 - 1978 and noted that there appeared to be no procedures in existence or planned in the following categories:

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I l.i. Access to Containment, l.m. Communications Systems, 4.j. Maintaining (Containment) Integrity, 4.x. Nuclear Instrument System (a)

Source Range (b)

Intermediate Range (c)

Power Range 6.d.

Loss of Core Coolant Flow, 6.k.

Loss of Protective Systems Channel, 6.1 Mispositioned Control Rod or Rods (and Rod Drops),

'.3.

Malfunction of Automatic Reactivity Control, 6.z. Intrusion of Demineralizer Resin Into Primary Systems For each of the above categories no procedures had been written or planned.

The need for a procedure in each of these categories will be further reviewed by the licensee.

A licensee representative stated that emergency and abnormal procedures (category 6) are symptom oriented and that they would make a determination if the conditions listed above were included in the existing procedures.

In addition, the inspector observed that there was a procedure for rod drops (EO-00-008);

however, a licensee representative stated that this procedure did not cover the broader aspect of mispositioned rods.

The inspector discussed each of the following with licensee representatives and a

summary of their comments appears after each category:

l.h. Record Retention A licensee representative stated that record retention procedures will be part of the Station Records Management System (SRMS) which has not yet been finalized, and that gA related procedures in the SRMS will receive PORC review.

1. k. Call-In of Personnel

- A licensee representative stated that procedure AD-gA-031 had been written in draft form to cover this topic.

5.

Procedures for Abnormal, Offnormal, or Alarm Conditions

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The inspector observed that procedures had not been identified for panel alarms not located in the Control Room.

A licensee representative stated that procedures would be written for these alarms, but they had not been identified as they had taken a lower priority than procedures for Control Room Panel Alarms.

6.v. Plant Fires The licensee representative noted that there were several fire protection procedures and plans, but would conduct a further review to ensure compliance with this category.

6.w. Acts of Nature (e.g.,

tornado, flood, dam fai lure, earthquakes)

A licensee representative stated that no procedure had been written to cover this area but a

procedure has been planned.

Each of the above items will be reviewed during a future NRC:RI inspection to ensure compliance with Regulatory Guide 1.33 (387/81-24-09).

(10) A licensee representative informed the inspector that procedure issuance was about SS percent complete but that all procedures required for OL would be issued by January 1982, including necessary revisions to previously approved procedures.

The inspector informed the licensee that further IE inspection of procedures would occur after 80 percent or greater of the procedures have been approved (287/81-24-10).

3.

Station Tour The inspector and the resident inspector toured the turbine building, con-tainment, and control room for Units

and 2.

The inspector observed the status and alarm conditions of certain systems are displayed on Cathode Ray Tubes (CRT's) in each control room.

The compliance to regulatory requirements for the use, control, and accuracy of information displayed on control room CRT's will be reviewed during a future NRC:RI inspection (387/81-24-11).

4.

Mana ement Meetin s

Licensee management was informed of the scope and purpose of the inspection at the entrance interview conducted on October 19, 1981.

The findings of the inspection were periodically discussed with licensee representatives during the course of the inspection.

An exit interview was conducted on October 23, 1981 (see paragraph 1 for attendees)

at which time the findings of the inspection were presented.