ML16341C017

Safety Evaluation Report Related to the Operation of Diablo Canyon Nuclear Power Plant,Units 1 and 2.Docket Nos. 50-275 and 50-323.(Pacific Gas and Electric Company)

ML16341C017
Person / Time
Site:	Diablo Canyon
Issue date:	08/31/1983
From:	Office of Nuclear Reactor Regulation
To:
References
NUREG-0675, NUREG-0675-S16, NUREG-675, NUREG-675-S16, NUDOCS 8309060116
Download: ML16341C017 (58)

Text

NUREG4675 Supplement No. 16 Safety Evaluation Report related to the operation of Diablo Canyon Nuclear Power Plant, Units i and 2 Docket Nos. 50-275 and 50-323 Pacific Gas and Electric Company Supplement No. 16 U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation

'ugust 1983

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ABSTRACT Supplement 16 to the Safety Evaluation Report has been prepared by the Office of Nuclear Reactor Regulation of the U.S.

Nuclear Regulatory Commission to address allegations received by the NRC staff concerning safety deficiencies

at the Diablo Canyon project relative to the design aspects of the component cooling water system.

Diablo Canyon SSER 16

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TABLE OF CONTENTS ABSTRACT.

ABBREVIATIONS 1

INTRODUCTION AND GENERAL DISCUSSION

1. 1 Introduction 9

AUXILIARYSYSTEMS 9.3 Water Systems 9.3.2 Component Cooling Water System APPENDIX A CONTINUATION OF CHRONOLOGY APPENDIX B

BIBLIOGRAPHY APPENDIX C

PRINCIPAL CONTRIBUTORS Pacae ill Vii

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1 1 9-1 9-1 9-1 Diablo Canyon SSER 16

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ABBREVIATIONS BTP CCWS FSAR GDC IDVP LOCA NRC RCP RG RHR Branch Technical Position component cooling water system Final Safety Analysis Report General Design Criteria(on)

Independent Design Verification Program loss-of-coolant accident Nuclear Regulatory Commission reactor coolant pump Regulatory Guide residual heat removal SER SRP SSE SSER Safety Evaluation Report Standard Review Plan (NUREG-0800) safe shutdown earthquake Safety Evaluation Report Supplement Diablo Canyon SSER 16 vii

1 INTRODUCTION AND GENERAL DISCUSSION

1. 1 Introduction On October 16,

1974, the Nuclear Regulatory Commission staff (the staff) issued a Safety Evaluation Report (SER)

(NUREG-0675) regarding. the'pplication by

'acific Gas and Electric Company (applicant) for licenses to operate the Diablo Canyon Nuclear Power Plant, Units 1 and 2.

Since that time, the staff has issued Supplements (SSERs) 1 through 15 to update the status of certain items identified in the SER.

On September 22, 1981, Facility Operating License No.

DPR-76 was issued to the applicant authorizing fuel loading and low: power testing for operation at up to 5X of rated power for Diablo Canyon Unit 1.

On November 19,

1981, the Commis-sion issued Order CLI-81-30, which suspended the low power license for Diablo Canyon Unit 1, following discovery of seismic design deficiencies and potential discrepancies in the facility's quality assurance program.

In addition, the NRC required the applicant to institute an independent design verification program (IDVP) that is part of a review by the NRC staff.

This supplement addresses certain allegations received by the staff concerning safety deficiencies at the Diablo Canyon project,'pecifically those relative to design aspects of the component cooling water system (CCWS), including its seismic classification, single failure considerations, and its heat removal capabilities.

It is based on the staff's re-'eview of the Diablo Canyon Final Safety Analysis Report (FSAR);

on a site walkdown conducted on January 12, 1983; on information obtain'ed during-meetings with the applicant on January 12, 1983 and April 19, 1983; and on letters from the applicant dated March 15, 18, and 25, April 4, 7, and 15; and May 3 and 18, 1983.

The NRC staff has addressed the following four points in this report:

(1)

CCWS Design Compliance With FSAR Commitments Through re-analysis of the heat removal capability of the

CCWS, assuming the worst design-basis heat load loss-of-coolant accident (LOCA) and the most limit-ing single failure, the applicant discovered a more limiting single failure than was determined in the original FSAR heat removal analysis.

Consequently, the applicant has provided the staff with additional information to show that this more limiting single failure was evaluated and that appropriate CCW heat removal capability for design-basis events can still be maintained.

With this action, the staff finds that the Diablo Canyon CCWS satisfies the original FSAR commitments with respect to design-basis events.

(2)

CCWS Design Compliance With Applicable NRC Regulations The staff finds that the requirements of General Design Criteria (GDC) 2, 44, 45, and 46 regarding protection against natural phenomena, cooling water capa-bility, in-service inspection and testing and that the guidelines of Regula-tory Guide (RG) l. 29 regarding seismic classification are now met.

The staff Diablo Canyon SSER 16

also concludes that the requirements of GDC 4 regarding environmental and missile effects are met.

(3)

CCWS Design Compliance With Criteria in the Current Standard Review Plan (SRP),

NUREG-0800, Section 9.2.2 Although the licensee deviates from current criteria as outlined in the Stan-dard Review Plan (SRP),

NUREG-0800, for moderate energy pipe break leakage

rate, and although the Diablo Canyon plant was not required to meet the

SRP, the staff has reviewed this deviation from SRP criteria and has found it technically acceptable.

(4)

Generic Implications of the Above Determinations Regarding Adequacy of the Diablo Canyon Design Approach and Philosophy

'he CCWS is the only safety-related closed loop cooling water system identified at Diablo Canyon that also serves nonessential components.

Thus, the concerns identified in this Supplement to the Safety Evaluation Report (SSER) that required subsequent re-evaluation should apply only to the

CCWS, and no generic implication is involved.

The sections of this supplement are designated the same as the sections of the SER that are being updated, and the discussions are supplementary to and not in lieu of the discussions in the

SER, unless otherwise noted.

The Project Manager for Diablo Canyon is Mr. Bartholomew C. Buckley; he may be'ontacted by calling (301) 492-8379 or by writing to the following address:

Mr. Bartholomew C. Buckley Division of Licensing U.S.

Nuclear Regulatory Commission Washington, D.C.

20555 Ms. Annette L. Vietti serves as Project Manager for the Diablo Canyon CCWS issue; she may be reached on (301) 492-4449.

Diablo Canyon SSER 16 1-2

9 AUXILIARYSYSTEMS 9.3.2 Component Cooling Water System The current acceptance criteria for the CCWS are General Design Criteria (GDC) 2, 5, 44, 45, and 46, as discussed in,.the Standard Review Plan (SRP),

NUREG-0800, Revision 2, dated July 1981, Section 9.2.2.

GDC 5 does not apply to Diablo Canyon because each unit has its own CCWS.

Although not so identified in SRP 9.2.2, all safety-related systems are also required to meet GDC 4.

This review is normally covered in other SER sections for all safety-related systems and would include the CCWS.

Although the SRP did not exist at the time of the original review, the above acceptance'riteria were applicable to Diablo Canyon at the time of its initial operating license review (1974) and apply as well as to current licensing review.

When the NRC staff evaluated Diablo Canyon, the CCWS design was evaluated against specific design criteria.

These criteria have changed to some extent since the initial Diablo Canyon review, as described in more detail below.

The following discussion compares the Diablo Canyon CCWS to the current acceptance criteria in SRP 9.2.2 and to the crite'ria as interpreted when Diablo Canyon was reviewed in 1974.

9. 3. 2. 1

System Description

The Diablo Canyon CCWS is designed to provide cooling water to essential and nonessential components and to operate in all plant operating modes--including normal power operation and plant cooldown--and in emergencies, including a loss-of-coolant accident (LOCA).

The CCWS consists of a baffled surge tank, three

pumps, two heat exchangers, and three cooling loops (vital loops A and B and nonvital loop C).

The CCWS is provided with redundant radiation monitors to detect inleakage of radioactive fluid from potentially radioactive components that are cooled by CCWS.

Makeup to the CCWS surge tank is normally provided by the nonseismic Category I demineralized water makeup system.

A seismic Category 'I source of makeup water is available at a rate of 250 gpm from the condensate storage 'tank via seismic Category I piping and the makeup water transfer

pumps, which are powered from the vital -emergency power supplies.

Additional nonseismic Category I makeup sources are also provided.

Two nor-mally isolated chemical addition tanks are provided, one on each pump discharge header.

The CCWS pumps are powered from the vital emergency power supplies.

Cooling water to the CCW heat exchangers is provided from redundant trains of the safety-related auxiliary salt water

system, which transfers

'the heat to the ultimate heat sink (the Pacific Ocean), 'thereby ensur'ing heat removal in all modes of operation.

One of the CCW heat exchangers is normally valved out by closing a motor-operated valve at the CCW heat exchanger outlet.

The three

'CWS pumps are normally headered together at the suction and discharge of the

'umps, with separation capability available via local manually operated valves.

Each pump is provided with a discharge line to two headers, one supplying vital Diablo Canyon SSER 16 9-1

loop A and one supplying vital loop B.

Thus, all three pumps are normally con-nected to both vital loops.

One CCM heat exchanger is located on each of these headers.

One or two CCW pumps are normally operating, with two-pump operation preferred.

Flow through header A from the pumps passes through CCW heat exchanger A, with a local, manually operated isolation valve at the inlet and a motor-operated valve at the outlet.

Header B is aligned in the same manner.

Downstream of the motor-operated isolation valves (one is normally closed),

headers A and 8

are cross-connected via two normally open local-manual isolation valves.

Down-stream of the header piping cross-connect, vital loops A and 8 supply their respective safety-related loads.

Between the two manually operated valves in the cross-connect piping, nonvital loop C is supplied via a normally open motor-operated valve.

Each vital loop (A and B) supplies cooling water to the following redundant safety-related components:

a charging pump lube oil and seal

cooler, a safety injection pump lube oil and seal

cooler, a residual heat removal (RHR) heat exchanger, an RHR pump seal

cooler, and containment air coolers.

Vital loops A

and B are identical, except that loop A supplies two containment, air coolers while loop B supplies

three, and loop A normally provides.cooling water to two CCW pump lube oil coolers and stuffing boxes while loop 8 provides cooling to one.

One train of the above components (including three containment air coolers) is required for safe shutdown under emergency (LOCA) operating conditions.

Nonvital loop C supplies cooling water to the following nonsafety-'related components:

spent fuel pool heat exchanger, letdown and excess letdown heat exchangers, steam generator blowdown heat exchangers, reactor coolant pump bearing oil coolers, seal coolers and seal water heat exchanger, sample heat exchanger, waste concentrator

coolers, boric acid evaporator coolers, auxiliary steam drain receiver vent condenser, reactor vessel support coolers, recipro-cating charging pump coolers, and waste gas compressor coolers.

These compo-nents are not required for safe shutdown. under emergency operating conditions.

9.3.2.2 Evaluation Seismic Classification FSAR Section 3 indicates that all CCWS piping and components are designed to seismic Category I requirements.

Further, the piping and essential components on vital loops A and B are equality Group C.

The piping and instrumentation diagrams show no design classification change at any CCWS components, including heat exchangers supplied by nonvital loop C.

However, the following statement, in FSAR Section 9.2.2 tends to contradict the above:

"Except for nonvital components in loop C and the chemical addition tanks, the CCM system is a Design Class 1 (seismic Category I) system."

The staff's original interpreta-tion of this statement assumed that "components" referred to the nonvital load itself, not the CCWS pressure-retaining portion of the component.

Therefore, it was assumed in the original staff review that the entire system, including the pressure-retaining portion of the Design Class II loop C components, was designed to seismic Category I criteria for pressure boundary-purposes.

Thus, a safe shutdown earthquake (SSE) would not cause a failure in the system that would result in loss of water, and isolation of loop C in an SSE was not con-sidered necessary.

The CCWS is located in seismic Category I structures, except Diablo Canyon SSER 16 9-2

for a portion located in the turbine building.

The applicant indicated in the FSAR that this. portion of the turbine building is designed not to fail in an SSE.

The issue of seismic integrity of the turbine building is being con-sidered by the staff as part of the Diablo Canyon IDVP, and a discussion can be found in NUREG-0675, Supplement 18.

The staff concluded in its original review that the requirements of GDC 44 regarding the CCWS cooling capability following an SSE were met.

The staff was informed in a meeting with the applicant on January 28,

1983, that this original conclusion may not have been correct and that the pressure-retaining portion of certain nonvital loop C components may not meet seismic Category I criteria, as the NRC staff originally assumed and as was confirmed by the applicant as the design basis for the CCWS.

In response to this concern, by letter dated May 18, 1983, the applicant verified that the pressure bound-aries of all nonvital loop C components have been re-analyzed to ensure their integrity under postulated SSE conditions.

Thus, a postulated single failure (to close) in the loop C supply remote-manual motor-operated valves will not result in an unacceptable condition, because isolation of the C loop following an SSE is not essential for ensuring the CCWS safety function.

Local manual action can be taken to close the valve as necessary.

After an

SSE, the operator would take local manual action to ti ansfer makeup to the CCW surge tank from the normal nonseismic Category I demineralized water makeup system to the seismic Category I condensate storage and transfer system.

Because there is no increase in leakage following an

SSE, no critical time constraint was placed on this manual action.

In addition, the NRC staff was informed during the January 28,

1983, meeting that the post-accident sample cooler recently added to vital loop A will be qualified to seismic Category I criteria.

As indicated

above, confirmation of the staff s original acceptance of the CCW design in this area has been provided.

Therefore, the staff concludes that the require-ments of GDC 2 and 44 and the guidelines of Positions C. 1 and C.2 of Regulatory Guide (RG) 1.29 regarding seismic classification are met.

Further discussion of the seismic qualification of the CCWS is included in the staff report on the Diablo Canyon IDVP (NUREG-0675, Supplement 18).

Leaka e Desi n

Because of the staff's original conclusion regarding the full seismic Category I qualification of the pressure boundary of the CCWS, acceptance of system leakage was originally based on a postulated nonmechanistic moderate energy pipe crack, which was the 200-gpm leak rate assumed by the applicant in the FSAR.

The leak rate is an important design consideration because system failure could occur upon excessive loss of water.

Thus, it is important to be able to detect'and mitigate such leakage promptly.

The applicant showed that the operator had 20 minutes under this assumed leakage condition to act and isolate nonvital loop C or separ ate the two vital loops to ensure proper CCWS operation.

To isolate loop C at the supply, the motor-operated isolation valve must be closed either remote-manually or local-manually, or the local manual cross-connect valves must be closed.

Because there are no check valves to isolate loop C at the return header, the two local manual cross-connect valves at the CCW pump suction must be closed.

Closing these valves renders one of the CCW pumps inoperable because it can take suction only from the loop C return header.

Similar manual actions are required'if the crack is assumed in either vital loop A or B.

No concurrent single failure is assumed with a moderate-energy Diablo Canyon SSER 16 9-3

pipe crack in a moderate-energy dual purpose system such as the Diablo Canyon

CCWS, as identified in the criteria of NRC Branch Technical Position (BTP)

ASB 3-1.

However, because of the size of the CCW loop headers--20 inches for the A, B, and C loops, and 30 inches for the A and B headers--a crack postulated in accordance with BTP ASB 3-1 would result in a higher flow rate than the assumed 200 gpm.

The applicant provided no bases or detailed evaluation for a maximum leak rate of 200 gpm.

Local manual valves must be closed at both the supply and return headers, or sufficient makeup provided to keep up with the loss of water.

To demonstrate compliance with current SRP criteria, the applicant would have to provide a more complete analysis showing (j.) that adequate time exists for operator action to prevent damage to all the CCW pumps on loss of suction and (2) that a temporary complete loss of CCWS flow while the operator realigns the system is acceptable, assuming the greater leak rates.

The staff noted in a field walkdown that the loops A, 8, and C supply valves are located in one area and are readily accessible for local manual operation as required.

Based on the criteria of BTP ASB 3-1, a leak rate of over 200 would have been postulated.

Nevertheless, the use of a 200-gpm leak rate satisfactorily demon-strated design capability because leak rates much lower than 200 gpm would be detected and action taken to isolate the leak before a leak rate of greater than 200 gpm would develop.

For this reason, system fai lure would not occur.

On this basis, the staff finds that GDC 4 and 44 are met with respect to leak detection and isolation capabilities.

Instrumentation Desi n

The instrument and control systems for the CCWS that perform safety functions are seismically and environmentally qualified.

The safety functions include those actions required for design-basis accidents.

In addition, the diagnostic instrumentation that provides indication of temperature and pressure to confirm that the CCWS is performing its safety function is also qualified for seismic and environmental conditions.

Instrumentation that does not perform a safety function and is connected to the CCWS is seismically qualified to ensure the pressure boundary of the CCWS.

As indicated previously, the applicant has veri-fied that the CCWS pressure boundary integrity is maintained following an SSE; thus no additional leakage following an SSE was assumed.

The applicant's origi-nal analysis indicates that operators have sufficient time to isolate.the non-vital components and thereby ensure the continued operability of the essential portions of the CCWS under the assumed nonmechanistic leak rate.

Low level alarms on the CCW surge tank would indicate that a failure of the CCWS pressure boundary had occurred.

The level switches and alarms were originally designed and installed to Class lE standards, including seismic qualification to ensure their operability following a seismic event.

Because no additional leakage is assumed to result from the

SSE, immediate operator action is unnecessary; thus the level instrumentation is not viewed as performing a safety function.

The operator can realign CCW surge tank makeup to the seismically qualified source some time after the earthquake.

Therefore, the CCW surge tank level indicator is classified as Class 1C under the Diablo Canyon instrument classification

system, which requires only that it maintain its pressure boundary following an SSE.

The staff finds the design and classification of the CCW surge tank level Diablo Canyon SSER 16 9-4

instrumentation acceptable because the integrity of the CCWS loop C pressure boundary is maintained following an SSE and immediate operator action is, there-

fore, unnecessary.

Missile Protection The missile spectrum identified by the applicant meets SRP criteria and is acceptable.

With the exception of the surge tank, the entire CCWS is located within tornado-missile-and flood-protected structures.

The system is located away from high-energy piping systems.

The CCWS pumps are located in separate

cubicles, thus providing protection from internally generated missiles.

The CCW surge tank is on the auxiliary building roof, 105 feet above ground, and is not fully protected against tornado missiles.

The applicant provided the results of analyses for the tank and its appurtenances.

The applicant assumes (FSAR Section

3. 3) that only one tornado missile acts at one time.

This assump-tion does not meet current criteria identified in SRP 3.5.2, which assume

,multiple missiles.

Further, the "safewind" (maximum mph for a given component) for the surge tank is below that identified in RG 1.76 for tornado Region II.

~

However, SRP 3.5. 1.4 criteria permit acceptance for tornado missile considera-tion on the basis of low probability as a substitute for the deterministic criteria of SRP 3. 5. 2.

The staff review concludes that the probability of tornado missile damage to the exposed CCW surge tank is sufficiently low and, therefore, is acceptable.

Based on the above, the staff concludes that the requirements of GDC 4 with respect to missile protection are met.

Heat Removal Ca abilit The applicant indicates in the FSAR that one CCW pump and heat exchanger is sufficient to provide decay heat removal and essential component cooling in the event of the most limiting accident, the design-basis LOCA with concurrent loss of offsite power and a single active failure.

In such an event, all three CCW pumps are automatically started, the motor-operated valve to the nonvital loop C

automatically closes (on receipt of a high containment pressure signal),

and the operator remote-manually opens the normally closed motor-operated valve to one CCW heat exchanger to put both in service.

Twenty minutes for operator action to perform this function is assumed.

In the long-term post-LOCA recir-culation phase, the operator also local-manually closes the loop A and B cross-connect valves to separate the CCWS into ful'ly redundant trains.

Because of the normally open cross-connection, flow to all five containment coolers is

provided, even though two are on loop A and three on loop B, as previously stated.

The FSAR CCWS heat removal analysis is based on a single failure of one emergency diesel generator (loss of one vital bus).

This is the most limiting failure from the standpoint of containment integrity following a LOCA because it results in a simultaneous loss of power to two containment,air coolers and one containment spray pump.

,The FSAR indicates that after a

LOCA under the above assumption, the CCM exit water temperature from.the containment air coolers is 216 F.

This is ata flow rate of 2000-gpm through each cooler and assumes that the nonvital loop is i,solated.

The applicant states in the FSAR that the CCM pressure is sufficient to prevent boiling in the CCWS at this temperature.

Return flow from the inoperative containment air coolers mixes with the 216 F water and results in reducing the bulk CCW return temperature to a value below the CCW pump suction design temperature of 171 F.

The staff Diablo Canyon SSER 16 9-5

accepted the above CCWS heat removal capability analysis in tne original SER and concluded that GDC 44 had been met.

However, concerns have been raised recently that the CCW heat removal analysis described above may not be the most limiting from the standpoint of CCW cooling

, performance and flow capacity and their effect on ensuring plant safety.

This is particular ly true if the operator fails to open the valve to the normally isolated CCW heat exchanger, because one heat exchanger will now experience full CCW pump flow and heat load for some time.

Further, the assumed vital bus single failure may not be limiting with respect to ensuring a maximum CCW temperature within design limits for equipment cooled by the system.

In response to these

concerns, by letters dated March 18, April 4, and May 18,

1983, the applicant" provided the results of a re-analysis of the heat removal capability of the

CCWS, assuming the worst design-basis heat load (LOCA) and the most limiting single failure.

From the standpoint of ensuring proper CCMS cooling performance to ensure acceptable equipment operation, it was determined that single failure of an auxiliary salt water pump results in a higher CCW temperature (with one CCM heat exchanger in operation) than was determined in the original FSAR heat removal analysis; thus it is more limiting.

To maintain CCW supply temperature at the maximum acceptable value of 132 F for equipment operation,.a maximum ocean water (auxiliary salt water system) temperature of 64 F must be assumed.

The FSAR analysis assumed an ocean water temperature of 70~F.

Consequently, the applicant has provided the following items to resolve this concern:

(2)

A Technical Specification on the 64~F ocean water intake temperature with appropriate surveillance, limiting conditions for operation, action state-"

ments, 'and bases.

The applicant has proposed actions such as valving in the second CCW heat exchanger or reducing plant power level when the intake temperature exceeds 64'F.

Verification that the accident analysis previously performed at an assumed 70 F ocean water temperature is not affected by a 64'F value.

(3)

Verification of acceptable CCWS per formance with two heat exchangers in operation under the new assumed conditions.

The staff finds the above acceptable for resolving these

concerns, because they ensure appropriate CCW heat removal capability for design-basis events.

The applicant has also provided further information that indicates that the design of the CCWS is such that there is only a small increase in flow rate through one CCW heat exchanger between two-and three-CCW-pump operation.

Further, CCWS pre-operational testing and flushing at excess flow rates has

'erified proper performance of the CCW and other safety-related heat exchangers under normal and accident conditions.

In addition, maximum CCW flow under design-basis conditions is, below the value identified'in the CCW heat exchanger specification, which was guaranteed by the equipment vendor.

Based on the above, the staff concludes that the applicant has provided ade-quate assurance of the CCW heat removal safety function and -therefore meets the requirements of GDC 44.

Diablo Canyon SSER 16 9-6

Reactor Coolant Pum Coolin Criteria for protection from a potential multiple-locked reactor coolant pump rotor event were developed and incorporated in the SRP after the original Diablo Canyon review.

The staff viewed such an occurrence as of sufficiently low probability to not require backfit to older plants, including Diablo Canyon.

Thus, the SRP criterion does not apply.

The staff previously reviewed Diablo Canyon against the criteria of Item II. K. 3. 25 of NUREG-0737 concerning reactor coolant pump seal cooling with loss of power and determined (as discussed in SER Supplement 14), that this capability is acceptable.

This determination is not affected by the present review.

Testin and Ins ection The CCWS operates continuously in all plant operating modes.

The pumps are rotated in service on a scheduled basis to obtain even wear and are periodi-cally tested and inspected in accordance with the plant Technical Specifica-tions.

The system components are located in accessible areas to permit inser-vice inspection as required.

Thus, the requirements of GDC 45 and 46 regarding inservice inspection and testing are met.

Conclusion Based on the staff's rereview of the CCWS and the applicant's re-analysis of CCWS heat removal capability, the staff now concludes that the CCWS satisfies the original FSAR commitments with respect to design-basis events.

Further the staff concludes that the CCWS now satisfies the requirements of GDC 2, 44, 45, and 46 regarding protection against natural phenomena, cooling water capabi 1-ity, inservice inspection, and testing, and the guidelines of RG 1. 29 regarding seismic classification.

The staff also concludes that the requirements of GDC 4 regarding environmental and missile effects are met.

The extent of de-viation of the CCW from current applicable criteria of SRP 9.2.2 was discussed previously in this supplement.

The only identified deviation from SRP 9.2.2 criteria is in the area of moderate energy pipe break leakage rate.

The staff has reviewed and accepted this deviation based on the applicant's satisfactory demonstration of design capability in this area.

It should also be noted that the CCWS is the only safety-related closed loop cooling water system identified at Diablo Canyon that also serves nonessential components.

Thus, the concerns identified above that required subsequent re-evaluation should apply only to the

CCWS, and no generic implication is involved.

Diablo Canyon SSER 16 9-7

APPENDIX A II CONTINUATION OF CHRONOLOGY April 1, 1981 Commission Order issued providing guidance to Boards on licensing proceedings.

April 2, 1981 April 6, 1981 Letter to applicant issuing SER Supplements 13 and 14.

Notice of Hearing to be held May 19-29,

1981, issued; published in the Federal Register April 13, 1981.

April 8, 1981 Letter from applicant providing information on emergency response facilities and onsite staffing levels in emergency situations.

April 16, l981 April 23, 1981 Letter to applicant concerning control system failures.

Letter from applicant forwarding certifications clarifying Charpy V-notch impact tests Apr,il 29, 1981 Letter from applicant providing confirmation of schedule for installation of reactor vessel indication system.

May 4, 1981 Letter to applicant transmitting RG l. 58, Revision 1, and RG 1.146.

May 5, 1981 Letter to applicant forwarding report on H.

B. Robinson reactor coolant system leak.

May 5, 1981 May 8, 1981 Letter to applicant concerning natural circulation cooldown.

Board Notification 81-06 issued on thermal >hock to PWR reactor pressure vessels.

May 13, 1981 Letter to applicant concerning emergency preparedness appraisal program.

May 19, 1981 Letter from applicant concerning submittal of information on control system failures.

May 27, 1981 Notice of Conference of Counsel to be held on July 1 and 2 issued; published in the Federal Register June 3, 1981.

May 28, 1981 Letter to applicant transmitting draft of Environmental Protection Plan (Appendix B to license, nonradiological).

May 29, 1981 Board Notification issued on emergency preparedness, full

- power operation.

Diablo Canyon SSER 16 A-1

June 4, 1981 Letter to applicant requesting copy of report issued by Institute of Nuclear Power Operations (INPO) be placed on docket.

June 4, 1981 Letter from applicant providing updated information on damage sustained by west breakwater.

June 10, 1981 Letter to applicant concerning results of operator licensing exams.

June 12, 1981 Letter from applicant transmitting Supplement 2 to "Diablo Canyon Unit 1 Radiation Shielding Review."

June 15, 1981 Letter to applicant regarding submittal of updated emergency plans.

June 16, 1981 June 17, 1981 Appeal Board Decision issued.

Letter from applicant transmitting further information on containment setpoint pressure.

June 25, 1981 Letter from applicant concerning existing emergency procedures and training programs for station blackout events.

June 29; 1981 Letter from applicant concerning adequacy of safety and relief valves based on preliminary review of Electric Power Research Institute (EPRI) test program results.

July 1, 1981 Letter to applicant forwarding "AEOD Observations and Recommendations Concerning the Problem of Steam Generator Overfill and Combined Primary and Secondary Side Blowdown."

July 3, 1981 Letter from applicant requesting exemption from Appendix J Paragraph III.D.2(b)(ii).

July 6, 1981 Letter to applicant advising that INPO reports will be handled by Regional Offices.

July 9, 1981 Letter to applicant. concerning. privacy and proprietary material in emergency plans.

July 9, 1981 Letter from applicant requesting modification to proposed Technical Specifications regarding containment ventilation system.

July 14, 1981 July 16, 1981 Letter from applicant concerning qualification of inspection, examination and testing, and audit personnel.

t Letter from applicant advising that guard training and qualification plans will be implemented no later than January 1, 1982.

Diablo Canyon SSER 16 A-2

July 16, 1981 Board Notification 81-15 issued on EPRI Relief 8 Safety Valve Testing Program.

July 17, 1981 July 17, 1981 Partial Initial Decision issued.

Letter to applicant concerning staff evaluation of TMI Action Plan Item I.C. l.

July 22, 1981 Letter from applicant transmitting containment structural integrity and leak rate test reports.

July 22, 1981 Letter from applicant advising that all masonry block walls now meet requirements of IE Bulletin 80-11.

July 23, 1981 July 31, 1981 Board Notification 81-16 issued on preoperational physical security inspection testing.

Letter'rom applicant concerning tests to demonstrate compliance'ith intent of RG 1.9.

August 7, 1981 August 10, 1981 Letter to applicant concerning simulator examinations.

Letter to app 1 icant concerni ng 1 ong-term, operabi 1 ity of deep draft pumps.

August 26, 1981 August 31, 1981 Meeting with applicant to discuss shift staffing requirements.

Letter to applicant concerning guard training and qualification plan instrumentation.

September 9,

1981 Appeal Board Decision issued (ALAB-653 and ALAB-653 RESTRICTED) on security.

September 10, 1981 Letter from applicant forwarding information on applicant's compliance with requirements of 10 CFR 20, 50, and 100.

September 14, 1981 Letter to applicant concerning diesel generator load tests.

September 14, 1981 Appeal Board Memorandum and Order issued re motions for stay of September 9,

1981 Decision.

September 15, 1981 September 21, 1981 Letter from applicant advising that construction activities are complete for Unit 1 and that construction activities should be complete for Unit 2 by July 4, 1982.

n Commission Memo and Order issued authorizing fuel load/low power license.

k September 22, 1981 Memorandum to Commission.

September 22, 1981 License DPR-76, fuel load and 5X power, issued.

Diablo Canyon SSER 16 A-3

September 23, 1981 Letter from 1 icensee transmi tting executed Indemni ty Agreement.

September 24, 1981 Letter from licensee transmitting information on control of heavy loads.

September 25, 1981 Meeting with licensee to discuss resolution of breakwater structure.

September 28, 1981 Letter from licensee transmitting Inservice Inspection and Testing Program Plan.

September 28, 1981 Letter from licensee transmitting Amendment 86, consisting of Revision 3 of Emergency

Plan, Corporate Emergency

Response

Plan, and Corporate Emergency

Response

Plan Procedures, procedures for Emergency

Plan, and "Earthquake Emergency Planning at Diablo Canyon."

September 29, 1981 Memorandum to Commission issued on potential deficiency in the seismic analysis of certain piPing systems (Board Noti-fication 81-27).

September 29, 1981 Letter to licensee (Generic Letter 81-36) issued on revised Schedule for Completion of TMI Action Plan Item II.D.1, Relief and Safety Valve Testing.

September 30, 1981 Mem'orandum to Commission issued on potential deficiency in the seismic analysis of certain piping systems (Board Notification 81-28).

October 2,,1981 October 9; 1981 Letter to licensee issuing SER Supplement 15.

Meeting with licensee to discuss adequacy of seismic design of certain piping systems.

October 14-16, 1981 Meeting with licensee to conduct audit review of seismic design of selected systems (summary dated October 19, 1981).

October 16, 1981 Memorandum to Commission forwarding transcript of October 9

meeting (Board Notification 81-29).

October 21, 1981'otice of Oral Argument to be held November 13, 1981.

October 21, 1981 Letter from licensee concerning IE Bulletin 79-15 on deep draft (verti cal turbine) pumps.

October 23, 1981 October 23, 1981 Memorandum to Commission forwarding meeting summary dated October 19, 1981 (Board Notification 81-33).

Memorandum to Commission forwarding FEMA Memorandum of October 7, 1981 (Board Notification 81-34).

Diablo Canyon SSER 16 A-4

October 23, 1981 Letter from licensee providing description of status and schedule of work being performed on seismic analysis review October 27, 1981 Letter from licensee concerning progress of work on seismic analysis.

October 28, '1981 Letter from licensee requesting exemption from definition:

of calendar quarter in 10 CFR 20.3(a)(4).

October 30, 1981 November 2, 1981 Meeting with licensee to discuss preservice inspection program.

Memorandum to Commission forwarding licensee's letter of October 23, 1981 and PNO-V-81-59 (Board Notification 81-35).

November 3,'981 Meeting with licensee to discuss progress of licensee's re-evaluation of potential seismic error of containment annulus area.

November 4, 1981 November 4, 1981 Memorandum to Commission forwarding PNO-V-81-54 and licensee's letters dated October 19 and 27, 1981 (Board Notification 81-36).

Memorandum to Commission forwarding transcript of November 3, 1981, meeting (Board Notification 81-37).

November 5, 1981 Memorandum to Commission forwarding report submitted by licensee on seismic reverification program (Board Notifica-.

tion 81-38).

November 6,

1981 Letter from licensee providing information on Emergency Operations Facility.

November 6, 1981 November 10, 1981 Letter from licensee forwarding'pdated information on implementing procedures for emergency plan.

~

r, Letter to licensee (Generic Letter 81-38) on storage of low-level radioactive wastes at power reactor sites.

November 12, 1981

-Notice of 'Change of Date of Oral Argument to November 20',

1981, issued.

November 13, 1981 Letter from licensee regarding additional work requirements for review of seismic analysis.

November 16, 1981 Board Notification 81-39 issued on meeting minutes dated May 18, 1967; on trenching conducted at site.

November 16, 1981 Board Notification 81-41 issued on ORNL report on pressurized thermal shock.

November 19, 1981 November 19, 1981 Order suspending license issued.

n Letter to licensee concerning independent design verification programs.

Diablo Canyon SSER 16 A-5

November 23, 1981 Letter from licensee transmitting security plan information.

November 25, 1981 Letter from licensee forwarding response to April 1, 1981, letter on potential deficiencies in bypass, override,,and reset circuits of engineered safety features.

November 30, 1981 Letter to licensee (Generic Letter 81-39) issued on NRC volume reduction policy.

November 30, 1981 November 30, 1981 December 4,.1981 Notice issued. of Conference of Counsel to be held December 16, 1981.

Board Notification 81-44 issued on breakwater damage.

Letter from licensee concerning the design verification program of. safety-related seismic analyses.

December ll, 1981 Board Notification 81-47 issued on the potential deficiency in the seismic analysis of equipment and components in the containment annulus.

December 14, 1981 Board Notification 81-51 issued on recent information in regard to the emergency preparedness plan.

December 16, 1981 Letter to licensee (Generic Letter 81-40) issued on

, qualifications of reactor operators, license examinations.

December 16, 1981 Notice issued of Hearing to be held January 19, 1982

~

December 17, 1981 Board Notification 81-54 issued on potential deficiency in the seismic analysis of equipment and components in the containment annulus.

December 18, 1981 Letter from licensee transmitting additional requests for

relief from ASNE Section XI requirements (PSI of bolting and ISI of welds).

December. 18, 1981 J

December 20, 1981 Letter from l,icensee transmitting requests for relief from PSI requirements for piping welds and secondary

vessels, and valves.

Il Letter from licensee transmitting, information on Emergency Operations Facility.

December 22, 1981 Letter from licensee concerning ongoing audit.

December 29, 1981 Letter from licensee requesting licensee amendment to extend the implementation dates for several items.

December 31, 1981 Letter to licensee in response to December 29, 1981, letter, granting extension.

Diablo Canyon SSER A-6

December 31, 1981 January 7,

1982 January 8,

1982 Letter to licensee authorizing exemption of definition of "calendar quarter" in 10 CFR 20.

Notice of, Receipt of 10 CFR 2.206 Petition re antitrust; Letter from licensee advising that no response is required to November,.19, 1981, submittal of draft report on reveri-,

fication program.

January 11, 1982 January 13, 1982 Letter from licensee regarding installation of containment hydrogen monitors.

l Letter from licensee transmitting Phase II program description:

(1)

"Design Verification Program for Power Ascension" and (2)

"qualification Document Design Verification Program for Power Ascension Diablo Canyon Power Plant Unit 1 Pacific Gas and Electric Company,"

Volumes 1, 2, and 3.

January 15, 1982 Letter from licensee transmitting five structural drawings presented at October 14-16, 1981 meeting.

January 19, 1982 January 20, 1982 Letter from l licensee concerning press release by Governor Brown concerning reverification program.

l Board Notification 82-04 issued on information item on recent information with regard to pressurized thermal shock.,

January 21,.',. 1982 W

January 22, 1982 January 27, 1982 January 27, 1982 January 28, 1982 Board Notification 82-05 issued on information item on potential deficiency,in the seismic analysis of equipment and components in the containment annulus of Diablo Canyon Unit 1 (transmitting PNO-V-82-03).

I Letter from licensee transmitting data for two piping seismic analyses.

Board Notification 82-06 issued on information item on applicant's submittal of design verification program, Phase II for Diablo Canyon Unit l.

Letter to licensee concerning review of security plan.

Letter to licensee concerning the proposed Reverification Program Plan.,

February 2, 1982 Letter to licensee concerning comment period for Phase II submittal of January 13.

February 3,

1982 Meeting with licensee to discuss issues based on staff review of December 4 submittal.,

February 5, 1982 Letter. from Teledyne regarding design reverification program.

r Diablo Canyon SSER 16 A-7

February 5,

1982 Amendment 1 to DPR-76 issued to extend implementation dates for certain items.

February 8, 1982 February 8, 1982 Letter to licensee (Generic Letter 82-02) issued on nuclear power plant staff working hours.

Board Notification 82-11 issued on potential deficiency in the seismic analysis of equipment and components in the containment annulus of Diablo Canyon Unit 1 (transmitting trip report on February 3, 1981).

February 10, 1982 February 10, 1982 February 12, 1982 February 17, 1982 Statement of the Commission on issuance of Notice of Violation.

Letter from licensee forwarding review team qualifications, task assignments, conflict of interest statements, and transcript corrections for minutes of February 3, 1982, meeting.

Letter from licensee-forwarding NPDES permit.

Meeting with Governor Brown and Joint Intervenors to discuss licensee's submittal of December 4 (transcript distributed March 3, 1982).

February 19, 1982 Board Notification 82-14 issued on information item on potential deficiency in the seismic analysis of equipment and components in the containment annulus of Diablo Canyon Unit 1 (transmitting meeting summary and other data from February 3, 1982, meeting).

February 23, 1982 Board Notification 82-16 issued on information item Infor-mation from R.

L. Cloud Associates on Design Verification Program for Diablo Canyon Unit l.'ebruary 23, 1982 February 24, 1982 Letter from R. L. Cloud advising that project has escalated to about '60;70K of recent billings'.

I n

~

Letter to ASLB from licensee concerning qualification of PORV and block values.

February 27, 1982 Letter R. L. Cloud listing service-safety-related contractors identified to date and transmitting "Seismic Reverification Program -

RLCA " Sample Selection."'arch 1,

1982 Letter-from licensee forwarding guality Assurance report of Myle Laboratories.

March 1, 1982 Letter from licensee fowar ding guality Assurance Review report of Anco Engineers.

March 1, 1982 Letter from licensee transmitting guality Assurance Review report of Cygna Energy Services.

Diablo Canyon SSER 16 A"8

March 2, 1982 Letter from licensee transmitting information submitted by Tel edyne.

March 3, 1982 March 5, 1982 Board Notification 82-19 issued on transcript of meeting with representatives of Governor Brown and of Joint Intervenors (forwarding transcript of February 17, 1982 meeting).

j Letter to licensee, Governor Brown, and J.

Reynolds requesting list of proposed contractors to perform design verification program.

March 5, 1982 Letter from R. F.

Reedy to R. L. Cloud forwarding guality Assurance Review report of URS/Blume.

March 8, 1982 Letter from R. F.

Reedy. transmitting licensee's assurance audit and review, report.

March 8, 1982 Letter from Teledyne suggesting that it is the logical selection as Program Manager for design verification program.

March 9, 1982 Letter to l,icensee (Generic Letter 82-04) issued on use of INPO SEE-IN Program.

March 10, 1982 March 11, 1982 March 12, 1982 March 12, 1982 Board Notification 82-23 issued on report of trip (February 22-26, 1982) regarding seismic design verification.

Letter from licensee transmitting safeguards information regarding security plan.

r Letter from licensee proposing Teledyne as the independent auditor.

il Letter to licensee requesting information necessary to initiate a determination of eligibility request to Keeper of National Register regarding area designated SL0-2.

March 12, 1982 Letter from licensee transmitting ninth, semimonthly status report.

March 15, 1982 March 15, 1982 March 15, 1982 March 17, 1982 Board Notification 82-24 issued on submittal by Teledyne Engineering Services regarding seismic verification program phase I for Diablo Canyon Unit l.

h Board Notification 82-25 issued on submittals from R. L. Cloud regarding the seismic verification program.

I Board Notification 82-26 issued on submittals by R.F.

Reedy regarding the seismic verification program.

Letter to licensee (Generic Letter 82-05) issued on Post-TMI Requirements.

March 18, 1982 Board Notification 82-10 issued on pressurized thermal shock.

Diablo Canyon SSER 16 A-9

March 19, 1982 Letter to licensee advising that staff has approved Tele-dyne as independent company to conduct design verification

program, phase I, with list of issues to be considered.

'arch 24, 1982 Board Notification 82-29 issued on 'information item-submittals by R. F.

Reedy and R. L. Cloud 'regarding the design verification program, phase 1, for Diablo Canyon Unit 1.

March 25, 1982 Meeting with licensee to discuss organizational structure for the design verification program, phases I and II, and to discuss issues pertaining to revisions of the Phase 1

program.'ar ch 31, 1982 Letter from licensee regarding proposal for EOF radio-logical monitoring system.

March 31, 1982 Letter from licensee concerning adequacy of the pressurizer safety and relief valves.

April 1, 1982 Meeting with licensee to discuss staff questions pertaining to the gA audit reviews performed by R.F.

Reedy, Inc.

April 2, 1982 April 2, 1983 Board Notification 82-33 issued on the seismic verification program.

Board Notification 82-34 issued on the seismic verification program (transmitting transcript of March 25, 1982 meeting)

Apr i 1 2, 1982 Letter from Teledyne transmitting independent design verification program, phase',

program management plan.

April 5, 1982 April 6, 1983 Letter from Teledyne forwarding program procedure draft of independent design verification program:

potential or apparent conflicts of interest of individuals.

Notice of Abnormal Occurrence issued on seismic design errors at Diablo Canyon Nuclear Power Plant.

April 6, 1982 Letter from licensee transmitting revised Overall Manage-ment Plan.

April 8, 1982 Letter from licensee transmitting piping schematics in connection with request for relief from certain inservice

'nspection requirements.

April 12, 1982 Letter from Teledyne concerning initiation of gA reviews and "design chain" actions.

April 12, 1982 Board Notification 82-36 issued on the seismic-verification program, transmitting transcript of April 1, 1982 meeting.

Diablo Canyon SSER 16 A-'10

April 13, 1982 Letter to licensee requesting complete computer listing of input and output of vertical seismic analysis.

April 15, 1982 Letter from licensee forwarding comments on March 8, 1982, Reedy report on gA.

April 15, 1982 Letter to licensee (Generic Letter 82-08) issued trans-.

mitting NUREG-0909 relative to the Ginna tube rupture'.

April 20, 1982 L'etter to licensee (Generic Letter 82-09) issued on environ-mental qualification of safety-related electrical equipment.

April 22, 1982 Letter from licensee forw'arding announcement and organi-zation chart on Bechtel's role.

April 26, 1982 April 26, 1982 Board Notification 82-42 issued on the design verification program transmitting April 10 Teledyne letter; April 9 Cloud letter; and April 8 Reedy letter.

Letter from licensee transmitting printout of input and output data of vertical seismic analysis.

April 27, 1982 April 28, 1982 April 30, 1982 April 30, 1982 L'etter to licensee advising of approval of Teledyne Phase I plan.

Letter from licensee transmitting piping schematics drawings.

Meeting with licensee to hear explanation of role that Bechtel will assume in completion of project, (summary dated May 18, 1982).

Board Notification 82-44 issued on the design verification program transmitting April '23.letters from Teledyne and Cloud and April 27 letter from Reedy.

May 5, 1982 Letter to licensee (Generic 'Letter 82-10) issued on post-TMI requirements.

May 6, 1982 Letter from licensee advising that revision to submittal of September 24,

1982, on heavy loads will be submitted at the end of August.

May 6, 1982 Letter to licensee concerning review of changes to security pl an.

May 8, 1982 Letter from Teledyne to licensee re additional verification and samples.

May 10, 1982 Letter from licensee advising of actions taken regarding generic concerns.

May 12, 1982 Letter from Center for Law in the Public Interest (Joint Intervenors) requesting issuance of order to show cause.

Diablo Canyon SSER 16 A-ll

May 13, 1982 May 24, 1982 Letter from licensee to Region V regarding DPR-76 conditions on physical security issues.

Board Notification 82-51, issued on the design verification program May 14 letters from Teledyne,

Cloud, and Reedy.

May 27, 1982 Letter from licensee transmitting Revision 11 of security plan.

May 28, 1982.,

Letter to licensee concerning security pl,an language.

May 28, 1982 Letter, from Teledyne advising that M.J. Holly has been designated as. civil structural consultant.

June 1,

1982 Letter from licensee regarding sequential auxiliary feed-water flow analysis.

June 2, 1982 June 4, 1982 Board Notification 82-53 issued on the design verification program (transmitting summary of April 30th meeting).

Letter from licensee in response to Generic Letter 82-10, transmitting resonse to some items; others to be sent 1 ater.

June 9, 1982 Letter to licensee (Generic Letter 82-1) issued transmitting NUREG-0916 on restart of Ginna.

June 9, 1982 June 10,

1982, Board Notification 82-57 issued on the design verification program.

h Meeting with licensee and Teledyne to discuss status of design verification program efforts, including schedules and gA program.

June ll, 1982 Letter from licensee transmitting final report on pipe supports base plate design.

June 16, 1982 Notice of Receipt of Petition Under 10 CFR 2.206 (J.

Reynolds).

June 17, 1982 Letter to licensee (Generic Letter 82-13) issued on reactor

.operator and senior react'or operator examinations.

June 18, 1982 Letter from Teledyne forwarding Independent Design Verification, Phase II, Program Management Plan.

June 18, 1982 Board Notification 82-60 issued on the design verification

program, Phase I, transmitting June 11 Teledyne letter, June 9 Cloud letter, and June 14 Reedy letter.

June 18, 1982 Board Noti.fication 82-61 issued on information items regarding the design verification program, Phase I.

Diablo Canyon SSER 16 A-12

June 21, 1982 Letter from 1 icensee tr ansmi tting changes to securi ty pl an.

June 23, 1982 Letter from licensee requesting license amendment for changing some dated requirements.

June 24, 1982 Letter from licensee advising that enough licensed operators to meet requirement of Item I.A.1.3.2. of Generic Letter 82-10 were available on September 22, 1981.

June 24, 1982 Letter from Teledyne transmitting second Phase I Interim Technical Report.

June 25, 1982 Board Notification 82-59 issued on steam generator tube rupture.

June 28, 1982 Letter from Teledyne advising of error in Interim Technical Report on gA.

June 29, 1982 Board Notification 82-62 issued on allegations concerning the Diablo Canyon Nuclear Power Plant.

June 30, 1982 Letter from California Regional Water equality Control Board forwarding copies of "Waste Discharge Requirements..."

and "Order No. 82-54 Amending NPDES Permit..."

July 1, 1982 Board Notification 82-66 issued on the design verification program transmitting letters from Teledyne and the licensee dated June 18.

July 1, 1982 Board~Notification 82-67 issued on Brookhaven report on its independent evaluation of Diablo Canyon design verification.

July 1, 1982 Board Notification 82-68 issued on the design verification program transmitting letter from Teledyne dated June 24..

July 2, 1982 Letter from licensee advising that License Condition 2.C(8)q on Long-Term Emergency Preparedness has been. met.

July 2, 1982 Letter to licensee (Generic Letter) on approval charter for the CRGR.

July 2, 1982 July 3, 1982 Letter to 1 icensee r egarding changes to security plan.

Letter from Teledyne transmitting Revision 1 to Phase I

Program Management Plan.

July 2, 1982 Board Notification 82-69 issued on the design verification program.

July 8, 1982 Letter from licensee to Teledyne regarding report by Brookhaven.

Diablo Canyon SSER 16 A-13

July 8, 1982 Letter to J.

Reynolds transmitting Teledyne letter=of June 18, 1982.

July 8, 1982 Letter to Governor Brown transmitting Teledyne letter of June 18, 1982.

July 8, 1982 Letter from Stone 8 Mebster advising that there are no open item report's'for repoi ting period ending July 9.

July 9, 1982 Letter from R.L. Cloud forwarding Open Item Reports

1094, 1095, and 1096, Revision 0.

July 9, 1982 Letter from Teledyne forwarding open item report system forms.

~

July 12, 1982 Letter from licensee transmitting completed form regarding certain archeological site.

July 12, 1982 July 16, 1982 Letter from licensee forwarding amended NPDES permit.

Letter from R. L. Cloud transmitting interim technical report -on tanks.

July 19, 1982 Letter from licensee transmitting amendment to security pl an.

July 21, 1982 Letter from, licensee transmitting supplemental information for,NUREG-0737,,Item II.F. 1 on noble gas effluent'monitors and sampling and analysis of plant effluents.

July 22, 1982 July 26, 1982-Board Notification 82-76 issued on the design verification

program, Phase I,'ransmitting'une 28 Teledyne letter, June 30 Reedy letter, July 7 Teledyne letter, and July 9

Teledyne and Reedy letters.

k Letter'from R. F.

Reedy advising there are no open item reports for the period July 10-25, 1982.

July 27, 1982 Meeting with licensee, Brookhaven, and Teledyne to exchange information and provide clarification regarding BNL report.

July 29, 1082 Board Notification 82-72 issued on information item with regard to Region IV investigation at Teledyne.

July 30, 1982 H

Commission Order releasing non-safeguard information of ALAB-653.

f July 30, 1982 August 2, 1982 Letter to licensee forwarding comments on proposed changes to security plan.

Board Notification 82-80 issued on information item regarding th'e design verification program, Phase I, forwarding Cloud letter of July 16.

Diablo Canyon SSER A-14

August 2, 1982 August 3, 1982 Letter to licensee forwarding comments on gA program.

Letter from licensee requesting extension of 1 year for expiration of license.

August 5, 1982 Letter from licensee forwarding Westinghouse

report, "Salem Unit 1 17 x 17 Fuel Assembly Guide Thimble Tube Wear Examination Report."

August 5, 1982 Letter from Teledyne forwarding program procedure for inter-face between IDVP participants 'and the licensee.

August 6, 1982 Meeting with licensee regarding current scope and status of the internal technical

program, the relationship of the program'o the IDVP, and of the schedule for the verifi-cation program; Teledyne will discuss current status and scope of IDVP.

August 9, 1982 August 9, 1982 Letter to licensee (Generic Letter 82-14) issued concern-ing, Submittal of Documents to the NRC.

Board Notification 82-75 issued on recent information with regard to accident-sequence precursor program report.

August 9, 1982 August 9, 1982 Letter from licensee requesting extension of CP date to September 30, 1983.

Letter 'from licensee'advising that completion of upgrading of plant vent radioactive particulates and gas monitoring system is anticipated by November 30, 1982.

August ll, 1982 Letter to Brookhaven forwarding items requested by Teledyne.

August 12, 1982 'etter from Stone

& Webster advising that is has issued no open item report's since July semimonthly report.

August 12, 1982 Board Notification 82-85 issued on the design verification

program, Phase I, for Diablo Canyon Unit 1 transmitting (1) trip report for May 25-28; (2) Cloud letter dated July 23; (3) Teledyne letter dated July 29 and (4) transcript of July 27 meeting).

August 12, 1982 Letter from licensee'ransmitting safeguards information relating to changes implemented to Revision ll of security pl an.

August 13, 1982 Letter from Teledyne transmitting Open Item Report System Forms.

August 13, 1982 Letter from R. F.

Reedy advising of no Open Item Reports for July 10 August 13.

Diablo Canyon SSER 16 A-15

August 13, 1982 Letter from R. L. Cloud transmitting Open Item Reports

1097, 1098, and 1099.

August 17, 1982 Board Notification 82-86 issued on the design, verification program (transmitting July 7 letter from Control Data to NRC).

August 18, 1982 Letter from licensee forwarding Reactor Containment Building Integrated Leak Rate Test Report.

August 19, 1982 Letter to Teledyne requesting additional information on Independent Design Verification Program.

August 19, 1982 Letter to licensee requesting information on Internal Techni cal Program.

August 19, 1982 Letter from R. L. Cloud transmitting Interim Technical Report on the Design Chain.

August 20, 1982 August 22, 1982 Letter from licensee, transmitting preliminary outline for Final Report for Phase I of design verification program.

1 Board Notification 82-81 issued on control rod drive tube support pin failures at Westinghouse plants.

August 24, 1982 Letter from licensee providing, lists of systems and equip-ment required for initial fuel loading and those systems and equipment that will provide operational, support during initial fuel load.

August 26, 1982 Letter from licensee concerning mechanical panel sealant requirements.

August 27.,

1982 Letter from licensee concerning future changes in Technical Specifications (regarding snubbers) due to verification pr ogram.

August 31, 1982 ASLB Initial Decision authorizing full power license.

September 1,

1982 Letter from licensee transmitting data on corrective action program.

September 1,

1982 Meeting with licensee and IDVP contractors to discuss activities within the PG&E Internal Technical

Program, including corrective actions, Phase I final report and status, inte-grated project schedule, and gA program, and to discuss status of the IDVP Phase I and Phase II.

September 1,

1982 Letter from licensee providing information on corrective action program and schedule.

September 3,

1982 Board Notification 82-91 issued on design verification program - Phase I (transmitting August 13 letters from

Teledyne, Cloud, and Reedy, Stone 8 Webster letter of August 12, and Cloud letter of August 19.

Diablo Canyon SSER 16 A-16

September:7, 1982 Letter from licensee advising that Teledyne'will conduct programmatic review of construction gA 'program as part of Phase II.

September 8,

1982 September 8,

1982 Letter from licensee transmitting listing of systems and equipment required for low temperature testing.

I Letter from licensee providing information on open items identi fied by the Inter nal Techni cal Program.

September 8,

1982 Letter to Teledyne advising of the acceptability of its procedure for ensuring the independence of individuals assigned to IDVP.

September 9,

1982 September 10, 1982 Meeting with representatives of Joint Intervenors and Governor Brown to discuss the IDVP Phase II plan, and the PG8E corrective action program.

Letter from Cloud submitting Interim Technical

Report, Diablo Canyon Unit 1 Independent Design Verification Program, Auxiliary Building, Revision 0.

September 14, 1982 Letter from California Office of Historic Preservation con-cerning archaeological site SL0-2..

September 14, 1982 September 15, 1982 Board Notification 82-95 issued on the design verification program Phase I, transmitting Teledyne letter of August 27 and transcript of September 2 meeting with licensee and Teledyne.

Letter from licensee forwarding responses to requests made at September 1 and 9

meetings.'eptember 17, 1982 September 17, 1982 Letter from Teledyne transmitting IDVP Program Procedure,

. "Potential or Apparent Conflicts of Interest of Individuals," Revision l.

t Letter from licensee transmitting request for license amendment re security plan.

i September 17, 1982 Letter from Teledyne transmitting Program Procedure Piping September 17, 1982 Support Baseplate and Anchor Bolt Evaluation, Revision 1.

Letter from R. L. Cloud transmitting Interim Technical Report on Raceway Supports, Revision 0.

-September= 17, 1982 Letter from licensee tramsmitting.additional sections of the Phase I Final Report.

September 20, 1982 Letter from licensee forwarding application for license amendment concerning 'upgrading emergency support, facilities.

Diablo Canyon SSER 16

'. A-17

September 20, 1982 Letter.to licensee (Generic Letter 82-16) on NUREG-0737, Technical Specifications.

September 21, September 22, September 23, 1982 1982 1982 Letter from licensee transmitting agreement for access to SLO-'2 site by Chumash Indian descendants.

lt Issuance of Director's Decision and Notice (re Joel Reynolds request).

I Letter from licensee advising that Westinghouse is to pro-

.vide analysis of reactor coolant system relief and safety valve qualification, (data for input to be provided before end of November 1982).

September 23, September 24, September 24, 1982 1982 1982 Letter from licensee transmitting updates to detailed Implementing Procedures for Emergency Plan.

e Board Notification 82-93 issued on Semiscale Test Results.

Memorandum to Commission on Diablo Canyon design verifica-tion program.

September 25, 1982 Letter from Teledyne transmitting Program Plan for Con-struction guality Assurance.

September 29,

'September 29, 1982 1982 Letter from Teledyne transmitting revised procedure on conflict of interest.

Board Notification 82-100 issued on the design verification program (tra'nsmitting Teledyne September 13 letter;

Reedy, Cloud, and"Stone 5 Webster, September 10 letters, Teledyne and Cloud September 17 letters.

September 29, 1982 Letter to Teledyne concerning independence of Teledyne and the need and desire to maintain communication.

September 30, 1982 October 1, 1982 October 1,

1982 Letter from licensee transmitting information on control of. heavy loads.

Letter from licensee regarding Generic Letter 82-12.

Letters to licensee.(Generic Letter 82-17) on inconsis-tency between requirements of 10 CFR 50.54(t) and Standard Technical, Specifications for Performing Audits of Emer-gency Preparedness Programs.

October 1, 1982 Letter from licensee transmitting sections of Phase I

Final Report and Revision 3 of outline for Phase I Final Report.

October 4,

1982, Letter to applicant regarding security plan.

Diablo Canyon SSER 16 A-18

October 5,

1982 Letter from Teledyne transmitting Program Plan for Con-struction Quality Assurance,,Revision l.

October 5, 1982 Letter from R. L. Cloud;transmitting Interim Technical Report on the Corrective Action Plan, Revision 0.

October 5,

1982 Letter to Teledyne regarding August 3 request for specific information items regarding Brookhaven Report.

October 6, 1982 October 6, 1982 Board Notification 82-101 issued on R.F.

Reedy, Inc.

Phase II QA Audits.

Board Notification 82-102 issued on the design verification program Phase I for Diablo, (transmitting Tel,edyne letters of Sepember 24 and 25).

October 6, 1982 Letter to Teledyne requesting preparation of assessment of basic cause of design errors,and include in final IDVP reports for Phases I and II.

October 6,, 1982 October 7, 1982 Letter to Teledyne forwarding summary of meeting and com-

, ments for September 10 QA.audit.

Letter, from Teledyne transmitting IDVP integrated (RLCA

.and TES) review comments to September 1,

1982 PG8E Phase I

Report.

October 8, 1982 Letter from R. L. Cloud advising that no Open Item Reports were issued during prior,.reporting period.

October 8, 1982 Letter from Tel,edyne forwarding Open Item Report System Forms issued by 'TES since September, 10 report.

October 8, 1982 i

October 8, 1982 Letter from Stone 8 Webster transmittng Open Item Report forms.

Letter from R. F.

Reedy advising that no Open Item Reports have been issued during September 10 - October 8.

October 11, 1982, Letter from Bechtel advising that Bechtel is not owned by

TES, RLCA, SWEC, or any of their subcontractors, and that Bechtel ho'lds no financial interest in any of those firms.

October 12, 1982 Letter from Teledyne providing clarification of request for "views" on required

systems, structures, and components for plant operating modes.

October 12, 1982 Letter from licensee transmitting supplemental information to July 19 request for license amendment.

October 13, 1982 Board Notification 82-104 issued on the Independent Design Verification, Program, transmitting Cloud letter of October 5.

Diablo Canyon SSER 16 A-19

October 13; 1982 Commission Paper SECY'82-414 issued on Diablo Canyon Design Verification Program, Phase II Recommendations.

October 14, 1982 Letter from Teledyne regarding employment of two former Sechtel employees.

October 15, 1982 October 15, 1982 October 15, 1982 Letter from Teledyne providing responses to Region V com-ments on Phase II activities.

Letter from Teledyne to PG8E advising of two concerns regarding consolidation of radial beams and local amplified response on tangential beams.

Letter from Teledyne prov'iding preliminary response to July 1 letter that transmitted Brookhaven report.

October 15, 1982 F

Letter from R. F.

Reedy 'transmitting Interim Technical Report (ITR-9) on development of safety-related contractor list for nonseismic work.

October'19, 1982 Meeting with licensee and IDVP contractors to discuss status of IDVP Phase I and Phase II issues.

October 21, 1982 Letter to Department of Interior requesti'ng determination of eligibility of Site SLO-'2 for inclusion in National Register.

October 22, 1982 Letter from Teledyne providing clarification of transcript of October 19 NRC-IDVP-DCP meeting.

October 22, 1982 October 25-26, 1982 Letter from R. L. Cloud transmitting Revision 1 to Interim Technical Report on Additional Verification and Additional Sampling.

Site visit and meeting with Bechtel regarding structures and equipment evaluated by BNL, (summary dated November 17, 1982).

October 26, 1982 Board Notification 82-109 issued on the design verification program transmitting Teledyne IDVP dated October 1; Teledyne IDVP Comments

'on Phase I Final Report, dated October 7;

Teledyne, Cloud,

Reedy, and Stone 5 Webster reports of October 8; and Teledyne letters of October 6, '12, 14, and 15 (2 letters).

October 26, 1982 October 26, 1982 October 27, 1982 Letter to licensee (Generic Letter 82-20) on implementing the standard review plan rule.

lf

'mendment 2 to DPR-.76 issued re security plan.

Letter to licensee transmitting (under separate cover) information sent to Teledyne on October 5.

Diablo Canyon SSER 16 A-20

November,l, 1982 November 1,

1982 Board Notification 82-110 issued on the design verifica-tion program, Phase I, transcript of October 19 meeting.

I Board Notification 82-112 issued on forwarding the Design Verification Program (transmitting Reedy letter of October 15; Teledyne letters of Ocrober 12 and 22, and Cloud letter of October 27).

November 1, 1982 Letter from licensee transmitting additional sections of Phase I Final Report.

November 3, 1982 Letter from Teldyne transmitting 11th Phase I Interim Techni cal Report.

November 3, 1982 Letter to Teledyne forwarding results of review of Interim Technical Reports 1 - 5.

November 5, 1982 Letter from R. L. Cloud transmitting Interim Technical Report No.

12 on Piping, Revision 0.

November 5,

1982 Letter from R. L. Cloud transmitting Interim Technical Report No.

13 on Soils-Intake Structure, Rev 0.

November 6,

1982 Letter from Teledyne transmitting IDVP Program Procedure DCNPP-IDVP-PP-007, Revision l.

C November 10, 1982 Board Notification 82-107 issued on semiscale test results.

November 12, 1982 Letter from Teledyne providing clarification of PP-007, Revision l.

Nobember 16, 1982 Board Notification 82-119 issued on the design verification program (transmitting Reedy letter of October 15, Cloud letters of October 19 and November 5, and Teledyne letter of November 3).

November 19, 1982 Letter from licensee transmitting additional sections of Phase I Final Report.

November 24, 1982 Board Notification 82-105 issued on alleged design deficiency.

November 24, 1982 Letter from licensee advising that due to lack of operating experience, meaningful answers cannot be provided for Gen-eric Letter 82-22.

November 24, 1982 Board Notification 82-120 issued on the design verification program.

November 22, 1982 Letter from Stone 8 Webster transmitting notes of con-ference for November 4 working meeting.

November 26, 1982 Letter from Teledyne forwarding "IDVP Semimonthly Report for November 1982."

Diablo Canyon SSER 16 A-21

November 29, 1982 Letter from licensee providing breakwater status update.

November 29, 1982 Letter from Teledyne advising of revised personnel assignments.

December 1,

1982 Letter from Teledyne to MHB Tech Associates on IDVP con-tact and documents.

December 1,

1982 Letter to licensee conder ning independent analyses to be performed by Brookhaven National Laboratory.

December 2,

1982 Letter from licensee forwarding schedules for fuel loading, low power testing, and full power license.

December 2,

1982 Letter to licensee requesting cl.arification on which gA program will be applied to what specific project activities.

December 3,

1982 Letter from licensee requesting restoration of low power license and stepwise licensing schedule to full power.

December 6,

1982 Letter form Teledyne advising of IDVP concurrence with licensee request for restoration of low power license and stepwise licensing schedule to full power.

December 6,

1982 Board Notification 82-127 issued on the design verification program.

December 7,

1982 Letter from licensee providing confirmation letter on features of permanent and interim Emergency Operations Facilities.

December 8, 1982 Board Notification 82-128 issued on the design verification program December 8, 1982 Letter from R. L. Cloud transmitting Interim Technical Re-port 16 on Soils-Outdoor Water Storage

Tanks, Revision 0.

December 10, 1982 Letter from licensee forwarding information on structural analysis for use by Brookhaven.

December 13, 1982 Letter from licensee concerning relief and safety valve test requirements.

December 13, 1982 Letter from R.L. Cloud transmitting Interim Technical Report 15 on HVAC Duct and Duct Supports, Rev.

0.

December 14, 1982 Board Notifications81-125 and 82-125A issued on ACRS evaluation of 'PWR flow blockage.

Diablo Canyon SSER 16 A-22

December 14, 1982 National Register of Historic Places Determination of EligibilityNotification for Archeological Site SL0-2.

December 15, 1982 Letter from R.

L. Cloud transmitting Interim Technical Report 17 on Piping, Additional Samples.

December 15, 1982 Letter from Stone 8 Webster transmitting Interim Technial Report 18, Revision 0.

December 16, 1982 Letter from licensee concerning modifications to be made to the fuel handling building.

December 17, 1982 Letter from licensee forwarding request for license amendment to change frequency for audit of emergency plan and security plan.

December 17, 1982 Letter from licensee regarding information needed by Brookhaven.

December 17, 1982 Letter from licensee forwarding additional sections of Phase I Final Report.

December 17, 1982 Letter to licensee (Generic Letter 82-33, Supp.

1 to NUREG-0737) issued on Emergency

Response

Capability.

December 21, 1982 Letter from licensee requesting temporary relief (120 days) from requirements of Tech Spec 3.9.7 to make modifications to fuel handling building.

December 21, 1982 Meeting withlicensee and Brookhaven; licensee to provide clarification and discuss the information provided by licensee for BNL containment annulus horizonal seismic analysis.

December 22, 1982 Board Notification 82-132 issued on the Design Verification Progr am, Phase I.

December 23, 1982 Commission Memorandum and Order issued.

December 28, 1982 Letter to licensee concerning two-step licensing approach.

December 29, 1982 Letter from licensee requesting Tech Spec change to permit modifications to vital 120 V ac inverters and associated busses.

December 30, 1982 Board Notification 82-138 issued on the Design Verification Program.

December 30,.1982 Letter from Stone 5 Webster transmitting Interim Technical Reports 17 and 18 regarding verification of IKC design of auxiliary feedwater system and control room ventilation and pressurization system.

Diablo Canyon SSER 16 A-23

January 4, 1983 Letter from licensee transmsitting part of information requested December 1 and transmitting information BNL requested at December 21 meeting.

January 5,

1983 Letter from licensee advising of deferral of breakwater repair activities.

January 6,

1983 Issuance of Amendment 3 to Facility Operating License DPR-76 (authorizing 120-day relief from Tech Specs 3/4.9.7 to make modifications to fuel handling building).

January 7,

1983 January 7,

1983 Boar d Notification 83-03 issued on notification of seismic qualification allegations.

Letter to Teledyne transmitting response by Brookhaven to request for information.

January 10, 1983 Letter from licensee transmitting three reports on potential consequences of degradation of the breakwater.

January ll, 1983 Letter from licensee requesting Tech Spec changes regarding overtime guidelines for shift workers and new reporting requirements.

January 12, 1983, Letter from R.

L. Cloud transmitting Interim Technical Report 30.

January 13, 1983 Board Notification 83-05 issued on the Design Verification Program.

January 14, 1983 Letter from R.L. Cloud transmitting Open Item Reports

1111, 1112, and 6001.

January 17, 1983 Letter,from R.

L. Cloud transmitting Interim Technical Report 31 on HVAC components.

January 18, 1983 Letter from Teledyne regarding additional sample and addi tiona1 verificati on.

January 18, 1983 Letter from Teledyne reporting on status of IDVP civil/

'tructural efforts.

January 19, 1983 Letter from licensee transmitting "Effects of Wave Forces on the Intake Structure" and "Investigations of Seawater Ingestion into the Auxiliary Saltwater Pump Room Due to Splash Run-up During the Design Flood Events at Diablo Canyon."

January 19, 1983 Letter to Teledyne transmitting January 6 transcript on alleged safety deficiencies.

January 19, 1983 Letter to licensee requesting information on pressure and temperature profiles for pipe break outside containment.

Diablo Canyon SSER.16 A-24

January 20, 1983 Letter from Stone 8 Webster transmitting Interim Technical Report No. 29, "Design Chain Initial Sample."

January 21, 1983 Letter from licensee transmitting additional sections of Phase I Final Repor t.

January 25, 1983 Letter to Bechtel from R.

F.

Reedy regarding IDVP design office verifications.

January 26, 1983 Letter to licensee advising of acceptability of Revisions 1 and 2 of gA program.

January 26, 1983 Letter to licensee regarding information items needed by BNL to perform analyses.

January 28, 1983 Meeting with licensee to discuss design and operation of the component cooling water system, and application of the single failure criteria.

February 3, 1983 Letter from Teledyne adivsing that Charles F.

Bergeron is now Lead Nuclear Technology Engineer.

February 3,

1983

/

February 4, 1983 Board Notification 83-10 issued on the design verification program.

Teledyne meeting with licensee,

NRC, and BNL to discuss status of containment annulus steelwork and status of auxiliary building.

February 4, 1983 Letter from licensee forwarding information regarding BNL information requests.

February 4, 1983 Letter from licensee forwarding information on pressure/

temperature profile analysis.

February 4, 1983 Letter from licensee transmitting Revision 2 to Security Force Training and gualification Plan.

February 4, 1983 Letter from licensee transmitting Revision 2 to Safeguards Contingency Plan.

February 4, 1983 Letter from licensee transmitting changes to Revision ll of Security Plan.

February 7, 1983 February 7-9, 1983 Letter from Stone 8,Webster transmitting "Verification of Diablo Canyon Project Efforts by Stone 8 Webster Engineering Corporation," Interim Technical Report 34.

Meeting with licensee to discuss Unit 1 Inservice Testing Program.

Diablo Canyon SSER 16

'" A-25

February 9, 1983 Teledyne meeting with R.

L. Cloud and licensee to discuss shake table tests of electrical equipment.

February 10, 1983 Letter from licensee requesting temporary relief from Tech Specs to perform boron mixing and cooldown tests under natural circulation conditions using decay heat.

February 10, 1983 Letter to licensee transmitting letter from Brookhaven requesting additional information for buried oil storage tank study.

February 11, 1983 Letter from licensee forwarding information requested by Brookhaven on February 4.

February 14, 1983 February 16, 1983 February 17, 1983 Meeting with Brookhaven on status -of seismic analysis efforts.

Letter from Brookhaven regarding PG&E Problem 8-118 and Westinghouse problem RHR Loop 4.

Letter from licensee transmitting sections and tables in Part 2 of Phase I Final Report.

February 17, 1983 Letter from licensee forwarding information on changes to be implemented in Security Plan, effective February 23.

February 17, 1983 Letter from R.

L. Cloud transmitting Interim Technical Report 32 on Pumps, Revision 0

~

February 18, 1983 Letter form R.

L. Cloud transmitting Interim Technical Report 33 on Electrical Equipment Analysis, Revision 0.

February 18, 1983 Letter from Teledyne requesting information for containment annulus structure analysis.

February 18,'983 Board Notification 83-17 issued on allegations relative to unresolved safety issue A-17.

February 23, 1983 February 23, 1983 Letter from R.

L. Cloud transmitting Interim Technical Report 37 on Valves, Revision 0.

Board Notification 83-22 issued on design verification program.

February 24, 1983 Notice issued on rescheduling'of oral argument to March 16, 1983.

February 24, 1983 Letter from Brookhaven listing items needing clarification on RHR Loop 4 and Problem 8-118 Piping.

February 24-25 1983 Teledyne meeting with licensee,

Cloud, and sta'ff to discuss structural review.

Diablo Canyon SSER 16 A-26

February 25, 1983 Letter from licensee f'orwarding pressure and temperature data for pipe break outside containment.

February 25, Febraury 25, 1983 1983 Letter from licensee forwarding request for license amendment on plant security plan.

Letter to licensee transmitting BNL requests dated February 16 and 24.

February 25, 1983 Letter from R.

L. Cloud transmi.tting Interim Technical Report 39 on Soils Intake Structure Bearing Capacity and Lateral Earth Pressure, Revision 0.

March 2, 1983 Letter from licensee transmitting changes to schedule for fuel loading, low power testing, and full power operation.

March 2, 1983 Letter from licensee transmitting information requested by Brookhaven.

March 3, 1983 Letter from Stone 8 Webster forwarding Interim Technical Reports 36, Revision 0, "Final Report on Construction equality Assurance Evaluation of Guy F. Atkinson Company,"

and 38, Revision 0, "Construction equality Assurance Evaluation of Wismer 8 Becker."

March 3, 1983 Board Notification 83-30 issued on changes to fuel loading schedule.

March 4, 1983 Letter from licensee transmitting FLUD 6 computer code steam blowdown input data necessary to calculate pressure and temperature transients in areas GE/GW of the auxiliary bui 1 ding.

March 4, 1983 Letter from licensee advising that it has installed appro-priately qualified monitors and electrical cable for vent radioactive gas and particulates monitoring system.

March 9, 1983 March 9, 1983 Notice issued of rescheduling of oral argument to April 14.

I Teledyne notice of meeting with OCP and IDVP on March 17 to review status of Phase II EOIs, determine additional verification requirement, and schedule for completion.

March 9, 1983 Letter to licensee transmitting draft technical evaluation report on control of heavy loads.

March 10, 1983 Letter from R.

L. Cloud transmitting Interim Technical Report 40 on Soils-Intake Structure Sliding Resistance.

March 11, 1983 March ll, 1983 Letter from l,icensee transmitting Phase II Status Report.

Exemption and Amendment 4 to DPR-76 issued (security plan).

Diablo Canyon SSER 16 A-27

March 14, 1983 Letter from licensee declining opportunity to participate in pilot inplant drill program.-

March 14, 1983 March 14, 1983 Letter from licensee regarding Item II.K.3.2 of NUREG-0737.

Letter from R.

F.

Reedy to licensee requesting that schedule be established for completion of design office verification on certain matters.

March 15, 1983 March 15, 1983 Letter from licensee transmitting sections and tables in Part 2 of Phase I Final Report.

Letter from licensee advising of schedule for providing information on component cooling water. system.

March 18, 1983 Board Notification 83-35 issued on the design verification program.

March 18, 1983 Letter from licenseee providing information on component cooling water system and advising that other information will be complete, by April 15.

March 18, 1983 Letter from Stone 5 Webster transmitting Interim Technical Report 38, Revision 1, "Final Report on Construction equality Assurance Evaluation of Wismer 8 Becker."

March 18, 1983 Letter from licensee forwarding piping information requested by Brookhaven.

March 22, 1983 March 22, 1983 March 22, 1983 Letter to licensee transmitting Generic Letter 82-38.

Letter from licensee advising that final temperature and pressure versus time curves will be sent by April 11.

Board Notification 83-38 issued on failure of GE AK-2

,reactor trip breakers.

March 24, 1983 Revised Teledyne notice of. March 17 meeting with. DCP 8

IDVP to review status of Phase II EOIs, determine additional verification requirement, and schedule for completion issued.

March 24, 1983 Letter to licensee forwarding guidance on reporting of offsite doses for 1982.

March 24, 1983 March 25; 1983 Letter from licensee in response to Generic Letter 83-10c.

.Letter from licensee forwarding information in response to BNL request for information on diesel fuel oil storage tanks.

4-(

Diablo Canyon SSER 16 A-28

March 25, 1983 March 25, 1983 Letter from licensee advising of schedule for submittal of information on component cooling water system.

Letter from licensee providing information on data collection relating to outages of emergency core cooling system components.

March 28, 1983 Letter from Stone 8 Webster transmitting Interim Technical Report 34, Revision 1, "Verification of Diablo Canyon Project Efforts by Stone and Webster Engineering Corporation."

March 28, 1983 Letter to licensee reqeusting information on archaeological site SL0-2.

March 29, 1983 April 1, 1983 Board Notification 83-41 issued on the design verification program.

Letter from R.

L. Cloud transmitting Interim Technical Report 32 on Pumps, Revision 1.

April 1, 1983 Letter from R.

L. Cloud transmitting Interim Technical Report 35, "IDVP Verification Plan for Diablo Canyon Project Activities," Revision 0.

April 4, 1983 Board Notification 83-44 issued on staff position regarding unresolved safety issue A-17.

April 4, 1983 Board Notification 83-47 issued on the need for rapid primary system depressurization capability in PWRs.

April 4, 1983 Letter from licensee providing additional inforamtion on the component cooling water system.

April 4, 1983 April 6, 1983 Board Notification 83-48 issued on allegations regarding Diablo Canyon.

Board Notification 83-49 issued on the design verification program.

April 7, 1983 Letter from licensee transmitting additional information on component cooling water system.

April 7, 1983 Letter from licensee transmitting report, "Startup Assistance Visit to Diablo Canyon Power Plant - January 25-30, 1982."

April 8, 1983 Letter from Teledyne transmitting "Interface Between IDVP and Participants,

DCP, and Designated Other Parties,"

Reivision 2.

April ll, 1983 Letter to licensee regarding February 4 submittal on contingency plan.

Diablo Canyon SSER 16 A-29

April ll, 1983 Letter to licensee regarding February 4 submittal on training and qualification plan.

April 12, 1983 Letter from California Dept of Justice transmitting state-ments by V. Tennyson and R.

Roam.

April 13, 1983 Meeting with licensee to discuss February 25 submittal on superstrut materi al.

April 13, 1983 Letter from licensee transmitting pressure and temperature transient analysis reports related to pipe breaks outside containment.

April 13, 1983 Letter from licensee transmitting drawings of annulus steel structure design.

April 14, 1983 Letter from R.

L. Cloud transmitting "Independent Design Verification Program, Heat Exchangers."

April 15, 1983 Board Notification 83-50 issued on the design verification pr ogr am.

April 15, 1983 Letter from licensee transmitting information on component cooling water system.

Apri 1 15, 1983 Letter from licensee regarding anonymous allegations on structural

adequacy, requesting opportunity to respond.

April 18, 1983 April 19, 1983 Letter from R.

L. Cloud transmitting Interim Technical Report 44 on Shake Table Test Mounting of Class 1E Electrical Equipment.

(

Meeting with licensee to discuss areas of review for component cooling water system.

April 19, 1983 Meeting with licensee to discuss component cooling water system (summary dated April 28, 1983).

April 21, 1983 Letter to D.

F 1 ei schaker on Mar ch 18 transmittal of anonymous allegations.

April 21, 1983 Appeal Board Memorandum and Order issued stating that record will be reopened on design and construction quality assurance matters.

April 22, 1983 Letter from R.

E.

Reedy forwarding "Corrective Action Program and Design Office Verification," ITR 41, Revision 0.

April 25, 1983 Letter from Stone

& Mebster transmitting (1) "Verification of the Mechanical/Nuclear Design of the Control Room Ventilation and Pressurization System,"

ITR 20, Revision Diablo Canyon SSER A-30

1 and (2) "Verification of the Mechanical/Nuclear Portion of the Auxiliary Feedwater System,"

ITR 22, Revision 1.

April 27-28, 1983 Teledyne meeting with NRC, RLCA, and DCP to discuss status of all structures.

April 27, 1983 Letter from licensee providing information on inadequate core cooling instrumentation system.

April 28, 1983 Letter from D. Fleischaker regarding anonymous allegations meeting with NRC.

April 29, 1983 Letter from R.

L. Cloud transmitting ITR 33, Revision 1, on electrical equipment analysis.

April 29, 1983 Letter from licensee requesting extension of expiration date for modifications to fuel handling building.

May 2, 1983 Letter to Cooper providing comments on ITR 36, Revision 0

and ITR 38, Revision lk.

May 2, 1983 Letter from Teledyne transmitting IDVP Final Report, Initial Text Submittal.

May 2, 1983 Letter from licensee requesting Tech Spec changes on containment isolation valves and other items.

May 3, 1983 May 3, 1983 Letter from D. Fleischaker regarding anonymous allegations.

Board Notification 83-56 issued on the design verification program.

May 3, 1983 Letter from licensee transmitting schedule for submittal of information on component cooling water system.

May 4, 1983 Letter from Stone

& Webster transmitting "Verification of the Auxiliary Feedwater System Electrical Design,"

ITR 25, Revision 1, and "Verification of the Control Room Ventilation and Pressurization System Electrical Design, ITR 26, Revision 1.

May 4, 1983 Board Notification 83-59 issued on NRC meeting with Pacific Gas

& Electric on Diablo Canyon's component cooling water system.

May 4, 1983 Meeting with licensee to discuss (1) status of design verification program and (2)

PG&E evaluation of eight recent allegations by an anonymous individual.

May 4, 1983 Board Notification 83-61 issued on the design verification program.

Diablo Canyon SSER A-31

May 5, 1983 Amendment 5 to DPR-76 issued (extending date from May 6 to June 20 for modification in fuel building).

May 5, 1983 Board Notification 83-55 issued on allegations regarding construction quality assurance.

May 9, 1983 Letter from licensee forwarding information on pressure/

temperature analysis for pipe break outside containment.

May 9, 1983 May 9, 1983 Letter from licensee transmitting report on heavy loads.

Letter from Stone 8 Webster transmitting "Verification of the Effects of High Energy Line Cracks and Moderate Energy Line Breaks for Auxiliary Feedwater System and Control Room Ventialtion and Pressurization System,"

ITR 21, Revision 1, and "Verification of the 4160 V Safety-Related Electrical Distribution System,"

ITR 24, Revision 1.

May 10, 1983 Letter from licensee transmitting "Pump and Valve Inservice Testing Program, Diablo Canyon Power Plant, Unit 1,"

Revision l.

May 11, 1983 Letter from applicant transmitting "Natural Circulation Boron Mixing Test," Revision 2, and pretest report.

May ll, 1983 Board Notification 83-65 issued on the design verification program.

May 12, 1983 Letter from Stone 8 Webster transmitting "Verification of the Pressure, Temperature, Humidity and Submergency Environ-ments Used for Safety-Related Equipment Specification Out-side Containment for Auxiliary Feedwater System and Control Room Ventilation and Pressurization System,"

ITR 14, Revision l.

May 12, 1983 Board Notification 83-68 issued on the design verification program (transmitting Final Report by Teledyne).

May 16, 1983 Letter from Teledyne transmitting second text submittal of IDVP Final Report.

May 18, 1983 Board Notification 83-69 issued on the Design Verification Program.

May 18, 1983 May 18, 1983 Appeal Board Decision (ALAB-728) issued.

Letter from licensee transmitting information on component cooling water system.

May 18, 1983 Letter from Stone 8 Webster transmitting ITR 17, "Verifica-tion of the Instrument and Control Design of the Auxiliary Feedwater System."

Diablo Canyon SSER 16 A-32

May 18, 1983 Letter from licensee transmitting updated sections of Phase I Final Report.

May 18, 1983 Letter form Stone 8 Webster transmitting ITR 28, Revision 1, "Verification of the Instrument and Control Design of the Control Room Ventilation and Pressurization System."

May 20, 1983 May 20, 1983 Letter from Teledyne transmitting Revision 3 of IDVP Program Procedure, "Interface Between IDVP Participants,

DCP, and Designated Other Parties."

1 Meeting with licensee and Westinghouse to discuss seismic qual ificati on of Main Control Board.

May 20, 1983 Letter from Stone 8 Webster transmitting ITR 45, "Additional Verification of Redundancy of Equipment and Power Supplies in Shared Safety-Related Systems."

May 25, 1983 Letter from J.

Reynolds regarding recent news report in San Luis Obispo County Telegram-Tribune.

May 26, 1983 May 27, 1983 Letter from Stone 8 Webster transmitting ITR 18, Rev 1, "Verification of the Fire Protection Provided for Auxiliary Feedwater

System, Control Room Ventilation and Pressurization

System, Safety-Related Portion of the 4160 V Electric System."

A Board Notification 83-76 issued on the design verification program.

May 31, 1983 Memo to Commission issued on the Status of Design Canyon Design Verifiction Effort.

June 2, 1983 Letter from Stone

& Webster transmitting ITR 23, Revision 1, "Verification of High Energy Line Break and Internally Generated Missile Review Outside Containment for Auxiliary Feedwater System and Control Room Ventilation and Pres-surization System."

June 2,

1983 June 3,

1983 Teledyne meeting with licensee to discuss various items.

'Board Notification 83-77 issued on allegation concerning release of draft NRC report.

June 3, 1983 Letter.to J; Reynolds'regarding potential pre-release of

'RC report.

June 3, 1983 Letter from Teledyne regarding IDVP review and position on DCP reevaluation of DCNPP turbine building and intake structure.

Diablo Canyon SSER 16 A-33

June 10.,

1983, Board Notification 83-78 issued on the design verification effort.

Diablo Canyon SSER 16 A-34

APPENDIX B BIBLIOGRAPHY U.S.

Nuclear Regulatory Commission, NUREG-0737, "Clarification of TMI Action Plan Requirements,"

November 1980.

---, NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants," July 1981.

Diablo Canyon SSER 16 B-1

tl.

APPENDIX C

PRINICIPAL CONTRIBUTORS Principal NRC staff contributors to this supplement were A. Vietti J

~

Lee J.

Mermiel T.

Dunning Project Manager Licensing Assistant Auxiliary System Branch Instrumentation

& Control Systems Branch Diablo Canyon SSER 16 C-1

U.S. NUCLEAR REGULATORY COMMISSION NRC FORM 335 BIBLIOGRAPHICDATA SHEET

4. TITLE AND SUBTITLE (Add Volume No.,i(appropriatei Safety Evaluation Report Related to the Operation of Diablo Canyon Nuclear Power Plant, Units 1 and 2

1. REPORT NUMBER (Assigned by DOCJ NUREG-0675 Supplement No. 16

2. (Leave blankJ

3. RECIPIENT'S ACCESSION No.

7. AUTHORIS)

5. DATE REPORT COMPLETED

9. PERFORMING ORGANIZATION NAME AND MAILINGADDRESS (include Zip CodeJ Division of Licensing Office of Nuclear Reactor Regulation U,ST Nuclear Regulatory Commission Washington, D.C.

20555 MONTH August DATE REPORT ISSUED MONTH August

6. (Leave blankJ

8. (Leave blankJ 1983 YEAR 19~3

12. SPONSORI JJG ORGANIZATION NAME AND MAILINGADDRESS (Include Zip Codel Same as 9. above

10. PROJECT/TASK/WORK UNITNo.

11. CONTRACT No, 13, TYPE OF REPORT PERIOD COVE RED (inclusive datesl

15. SUPPLEMENTARY NOTES Docket Nos. 50-27$ and 50-323

14. (Leave olankJ

16. ABSTRACT (200 words or lessJ Supplement No. 16 to the Safety Evaluation Report for Pacific Gas and Electric Company's application for licenses to operate the Diablo Canyon Nuclear Power Plant (Docket Nos. 50-275 and 50-323) located in San Luis Obispo County, California has been prepared by the Office of Nuclear Reactor Regulation of the U.S. Nuclear Regulatory Commission.

This supplement provides recent information, concerning the Diablo Canyon component cooling water system.

17, KEY WORDS AND DOCUMENT ANALYSIS 17a, DESCRIPTORS 17b. IDENTIFIERSJOPEN ENDED TERMS

18. AVAILABILITYSTATEMENT Unlimited IIJ RC FORM 335 (7 771

19. SECURITY CLASS (Thts report/

U

20. SECURITY CLASS (7'hts paeeJ Unclassified

21. No. OF PAGES

22. PRICE S

v